REQUEST 10000 20000218 1000000000000 ENTRY 10001 19991011 10001 0 1 SUBENT 10001001 19991011 10001 1 1 BIB 8 15 10001 1 2 INSTITUTE (1USALAS) 10001 1 3 REFERENCE (W,T.ETHVIGNOT) THE REPORT ON THE 2RCM OF CRP ON 10001 1 4 "FISSIM PRODUCT YIELD DATA REQUIRED FOR TRANSMUTATION 10001 1 5 OF MINOR ACTINIDE NUCLEAR WASTE" 10001 1 6 AUTHOR (G.D.JOHNS, R.O.NELSON, W.S.WILBURN, D.M.DRAKE, 10001 1 7 D.E.ARCHER, J.A.BECKIER, L.A.BERNSTEIN, P.E. GRARRETT, 10001 1 8 D.P.MCNABB, W.YOUNES, T.ETHVIGNOT, T.GRANIER) 10001 1 9 TITLE HIGH ENERGY NEUTRON INDUCED FISSION: FRAGMENT YIELDS 10001 1 10 AND NEW ISOMERS 10001 1 11 FACILITY (LINAC) 10001 1 12 INC-SOURCE (SPALL) WNR SPALLATION NEUTRON SOUNE WITH PROTON ENERGY10001 1 13 OF 800 MEV. 10001 1 14 METHOD (TOF) 10**6N/CM**2/S 10001 1 15 DETECTOR SOLAR CELLS FOR FISSION FRAGMENT DETECTION INSIDE 10001 1 16 GEANIE (GERMANIUM ARRAY FOR NEUTRON INDUCED EXITATIONS)10001 1 17 ENDBIB 15 0 10001 1 18 NOCOMMON 0 0 10001 1 19 ENDSUBENT 18 0 10001 199999 SUBENT 10001002 19991011 10001 2 1 BIB 3 7 10001 2 2 REACTION (92-U-238(N,F)40-ZR-102,CUM,FY,,REL) 10001 2 3 FLAG (1.) ARITHMETICAL MEAN FROM,TWO SETS OF DATA, WHOSE ERR10001 2 4 ARE APPROXIMATELY SAME 10001 2 5 (2.) WEIGHED MEAN FROM TWO SETS OF DATA, WHOSE ERRORS A10001 2 6 QUITE DIFFERENT 10001 2 7 COMMENT THE DATA WERE READ FROM FIGURE 10001 2 8 THE DATA ARE PRIMARY ONES. 10001 2 9 ENDBIB 7 0 10001 2 10 NOCOMMON 0 0 10001 2 11 DATA 4 23 10001 2 12 EN DATA DATA-ERR FLAG 10001 2 13 MEV ARB-UNITS ARB-UNITS NO-DIM 10001 2 14 1.25 0.050 0.006 10001 2 15 1.75 0.211 0.011 10001 2 16 2.25 0.230 0.012 1. 10001 2 17 2.75 0.211 0.012 1. 10001 2 18 3.5 0.202 0.011 10001 2 19 4.5 0.175 0.011 10001 2 20 5.5 0.180 0.011 1. 10001 2 21 6.5 0.234 0.012 1. 10001 2 22 7.5 0.263 0.013 1. 10001 2 23 8.5 0.252 0.014 1. 10001 2 24 9.5 0.225 0.018 1. 10001 2 25 11.5 0.239 0.014 10001 2 26 14.0 0.289 0.014 1. 10001 2 27 16.0 0.271 0.018 1. 10001 2 28 18.0 0.301 0.018 2. 10001 2 29 22.5 0.226 0.017 2. 10001 2 30 27.5 0.203 0.020 1. 10001 2 31 32.5 0.186 0.021 10001 2 32 37.5 0.143 0.021 10001 2 33 45.0 0.130 0.025 10001 2 34 55.0 0.105 0.014 10001 2 35 70.0 0.0643 0.014 10001 2 36 115.0 0.0643 0.009 10001 2 37 ENDDATA 25 0 10001 2 38 ENDSUBENT 37 0 10001 299999 ENDENTRY 2 0 1000199999999 ENTRY 10002 19921015 10002 0 1 SUBENT 10002001 19921015 10002 1 1 BIB 6 8 10002 1 2 INSTITUTE (1USALAS) 10002 1 3 REFERENCE (J,BAP,37,(5),1300,9210) 10002 1 4 AUTHOR C.ZOELLER, A.GAVRON, J.P.LESTONE, M.MUTTERER, 10002 1 5 J.P.THEOBALD, A.CARLSON, G.PETITT 10002 1 6 TITLE THE 238(N,F) REACTION AT INCIDENT NEUTRON ENERGIES 10002 1 7 FROM 1 TO 200 MEV 10002 1 8 FACILITY (LINAC) 10002 1 9 INC-SOURCE WNR SPALLATION WHITE NEUTRON SOURCE AT LANL EN=1-200MEV10002 1 10 ENDBIB 8 0 10002 1 11 NOCOMMON 0 0 10002 1 12 ENDSUBENT 11 0 10002 199999 SUBENT 10002002 19921015 10002 2 1 BIB 1 4 10002 2 2 REACTION 1(92-U-238(N,F)ELEM/MASS,CHN,FY) 10002 2 3 2(92-U-238(N,F)ELEM/MASS,,KE,FF) 10002 2 4 1. FISSION FRAGMENT MASS DISTRIBUTION 10002 2 5 2. FISSION FRAGMENT KINETIC ENERGY DISTRIBUTION. 10002 2 6 ENDBIB 4 0 10002 2 7 NOCOMMON 0 0 10002 2 8 NODATA 0 0 10002 2 9 ENDSUBENT 8 0 10002 299999 ENDENTRY 2 0 1000299999999 ENTRY 10357 860723 10357 0 1 SUBENT 10357001 860723 10357 1 1 BIB 9 12 10357 1 2 INSTITUTE (1USAARK) 10357 1 3 REFERENCE (J,JIN,34,2405,7208) 10357 1 4 AUTHOR (S.A.RAO) 10357 1 5 TITLE ISOMER YIELD RATIOS OF CD-115M AND CD-115G. 10357 1 6 FACILITY (CCW) COCKCROFT-WALTON 10357 1 7 METHOD (CHSEP) 10357 1 8 DECAY-DATA (48-CD-115-M,43.D,B) 10357 1 9 (48-CD-115-G,2.3D,B) 10357 1 10 ERR-ANALYS NO INFORMATION 10357 1 11 HISTORY (740603C) 10357 1 12 (830422A) CONVERTED TO REACTION FORMALISM 10357 1 13 (860723A) BIB UPDATE. 10357 1 14 ENDBIB 12 10357 1 15 COMMON 1 3 10357 1 16 EN 10357 1 17 MEV 10357 1 18 14.8 10357 1 19 ENDCOMMON 1 3 10357 1 20 ENDSUBENT 1 10357 199999 SUBENT 10357004 860723 10357 4 1 BIB 3 3 10357 4 2 REACTION (90-TH-232(N,F)48-CD-115-M/G,CUM,FY/RAT) 10357 4 3 SAMPLE TH(NO3)4. 10357 4 4 HISTORY (860723C) 10357 4 5 ENDBIB 3 10357 4 6 NOCOMMON 0 0 10357 4 7 DATA 2 1 10357 4 8 DATA DATA-ERR 10357 4 9 NO-DIM NO-DIM 10357 4 10 0.088 0.015 10357 4 11 ENDDATA 3 10357 4 12 ENDSUBENT 2 10357 499999 SUBENT 10357005 860723 10357 5 1 BIB 3 3 10357 5 2 REACTION (92-U-238(N,F)48-CD-115-M/G,CUM,FY/RAT) 10357 5 3 SAMPLE URANYL NITRATE. 10357 5 4 HISTORY (860723C) 10357 5 5 ENDBIB 3 10357 5 6 NOCOMMON 0 0 10357 5 7 DATA 2 1 10357 5 8 DATA DATA-ERR 10357 5 9 NO-DIM NO-DIM 10357 5 10 0.12 0.02 10357 5 11 ENDDATA 3 10357 5 12 ENDSUBENT 2 10357 599999 ENDENTRY 3 1035799999999 ENTRY 10433 810529 10433 0 1 SUBENT 10433001 801027 10433 1 1 BIB 11 15 10433 1 2 INSTITUTE (1USAARK) 10433 1 3 REFERENCE (J,JIN,37,1341,7506) 10433 1 4 AUTHOR (W.D.JAMES,D.E.ADAMS,J.N.BECK,P.K.KURODA) 10433 1 5 TITLE INVESTIGATION OF THE REPORTED MASS DISTRIBUTION CURVES 10433 1 6 IN THE FISSION OF 233-U WITH 14.8 MEV NEUTRONS. 10433 1 7 FACILITY (CCW) 400 KV COCKCROFT-WALTON ACCELERATOR 10433 1 8 METHOD (ACTIV) BETA ACTIVITY OF FISSION PRODUCTS 10433 1 9 DETECTOR GAS FLOW BETA COUNTER 10433 1 10 CORRECTION DATA CORRECTED FOR SELF-SCATTERING AND SELF-ABSORPTION 10433 1 11 IN EACH NUCLIDE 10433 1 12 ERR-ANALYS DATA ERRORS GIVEN ARE MAINLY STATISTICAL ERRORS AND 10433 1 13 DECAY CURVE RESOLUTION UNCERTAINTIES 10433 1 14 STATUS NO AUTHOR REPLY 10433 1 15 HISTORY (750529C) 10433 1 16 (801027A) CONVERTED TO REACTION FORMALISM. 10433 1 17 ENDBIB 15 10433 1 18 NOCOMMON 0 0 10433 1 19 ENDSUBENT 0 10433 199999 SUBENT 10433002 810529 10433 2 1 BIB 4 13 10433 2 2 REACTION (92-U-233(N,F)ELEM/MASS,CUM,FY) 10433 2 3 MONITOR (92-U-233(N,F)42-MO-99,CUM,FY) 10433 2 4 (92-U-233(N,F)52-TE-132,CUM,FY) 10433 2 5 DECAY-DATA ((1.)46-PD-109-G,13.46HR,B) 10433 2 6 ((2.)46-PD-112,20.1HR,B) 10433 2 7 ((3.)47-AG-111-G,7.47D,B) 10433 2 8 ((4.)47-AG-113-G,5.3HR,B) 10433 2 9 ((5.)48-CD-115-G,53.5HR,B) 10433 2 10 ((6.)50-SN-121-G,26.8HR,B) 10433 2 11 ((7.)51-SB-127,3.8D,B) 10433 2 12 ((8.)56-BA-140,12.79D,B) 10433 2 13 HALF-LIFE VALUES GIVEN BY AUTHORS 10433 2 14 HISTORY (810529A) DECAY-DATA CORRECTIONS. 10433 2 15 ENDBIB 13 10433 2 16 COMMON 3 3 10433 2 17 EN MONIT1 MONIT2 10433 2 18 MEV PC/FIS PC/FIS 10433 2 19 14.8 3.87 3.73 10433 2 20 ENDCOMMON 3 3 10433 2 21 DATA 5 8 10433 2 22 ELEMENT MASS DATA DATA-ERR DECAY-FLAG 10433 2 23 NO-DIM NO-DIM PC/FIS PC/FIS NO-DIM 10433 2 24 46. 109. 1.79 0.20 1. 10433 2 25 46. 112. 1.90 0.11 2. 10433 2 26 47. 111. 1.77 0.18 3. 10433 2 27 47. 113. 1.70 0.15 4. 10433 2 28 48. 115. 1.57 0.20 5. 10433 2 29 50. 121. 2.02 0.38 6. 10433 2 30 51. 127. 2.55 0.34 7. 10433 2 31 56. 140. 5.67 0.58 8. 10433 2 32 ENDDATA 10 10433 2 33 ENDSUBENT 5 10433 299999 ENDENTRY 2 1043399999999 ENTRY 10712 810529 10712 0 1 SUBENT 10712001 891113 10712 1 1 BIB 15 34 10712 1 2 INSTITUTE (1USALRL) 10712 1 3 REFERENCE (J,PR/C,16,1907,7711) 10712 1 4 (J,PR/C,20,1824,7911) CORRECTIONS TO DATA. 10712 1 5 AUTHOR (D.R.NETHAWAY,A.L.PRINDLE,W.A.MYERS,W.C.FUQUA, 10712 1 6 M.V.KANTELO) 10712 1 7 TITLE FISSION OF PU-240 WITH 14.8-MEV NEUTRONS. 10712 1 8 FACILITY (ICTR). 10712 1 9 INC-SOURCE (D-T) 400-KEV DEUTERONS ON A ROTATING TITANIUM 10712 1 10 TRITIDE TARGET. 10712 1 11 SAMPLE PU-O(2) SAMPLE. ISOTOPIC COMPOSITION - 10712 1 12 PU-238 - 0.17 PERCENT 10712 1 13 PU-239 - 0.67 PERCENT 10712 1 14 PU-240 - 98.39 PERCENT 10712 1 15 PU-241 - 0.55 PERCENT 10712 1 16 PU-242 - 0.37 PERCENT 10712 1 17 METHOD (RCHEM) 10712 1 18 DETECTOR (GELI) GE(LI) DETECTORS FOR GAMMA-RAY SPECTROSCOPY. 10712 1 19 (PROPC) GAS-FLOW PROPORTIONAL COUNTERS FOR BETA- 10712 1 20 PARTICLE ASSAY. 10712 1 21 MONITOR ((MONIT)94-PU-240(N,F)42-MO-99,CUM,FY) 10712 1 22 NUMBER OF FISSIONS OCCURRING CALCULATED FROM THE 10712 1 23 PU-240/U-238 FISSION CROSS SECTION RATIO=1.98+-0.06 10712 1 24 AND THE NUMBER OF U-238 FISSIONS. 10712 1 25 CORRECTION MEASURED AMOUNT OF EACH FISSION PRODUCT CORRECTED FOR 10712 1 26 DECAY BACK TO END OF IRRADIATION AND FOR DECAY DURING 10712 1 27 IRRADIATION. 10712 1 28 ERR-ANALYS SYSTEMATIC ERROR IN YIELD DETERMINATION +-4 PERCENT. 10712 1 29 ADD-RES TOTAL CHAIN YIELDS CALCULATED FROM MEASURED FISSION 10712 1 30 YIELDS USING Z(P) VALUES FROM UCRL-51640 (1974). 10712 1 31 STATUS (APRVD) D.R.NETHAWAY 78/2/17. 10712 1 32 HISTORY (780112C) 10712 1 33 (801028U) BIB CORRECTIONS. 10712 1 34 (810309A) REFERENCE ADDED. 10712 1 35 (891113A) BIB, COMMON CORRECTIONS. 10712 1 36 ENDBIB 34 10712 1 37 COMMON 4 3 10712 1 38 EN EN-RSL MONIT MONIT-ERR 10712 1 39 MEV MEV PC/FIS PER-CENT 10712 1 40 14.8 0.3 4.85 5. 10712 1 41 ENDCOMMON 4 3 10712 1 42 ENDSUBENT 4 10712 199999 SUBENT 10712002 810529 10712 2 1 BIB 4 121 10712 2 2 REACTION (94-PU-240(N,F)ELEM/MASS,CUM,FY) 10712 2 3 DECAY-DATA ((1.)28-NI-66,54.6HR,B) 10712 2 4 ((2.)29-CU-67,2.575D,DG,91.23,0.0683,DG,93.29,0.161, 10712 2 5 DG,184.56,0.487) 10712 2 6 ((3.)30-ZN-72,46.5HR,DG,144.7,0.83) 10712 2 7 ((4.)31-GA-73,4.91HR,DG,295.,0.77, 10712 2 8 DG,328.,0.135) 10712 2 9 ((5.)36-KR-87,1.267HR,DG,402.47,0.473, 10712 2 10 DG,2554.92,0.0847) 10712 2 11 ((6.)36-KR-88,2.803HR,DG,2195.90,0.141, 10712 2 12 DG,2392.10,0.379) 10712 2 13 ((7.)38-SR-89,50.55D,B) 10712 2 14 ((8.)38-SR-90,28.6YR,B) DETERMINED BY MILKING OF THE 10712 2 15 2.66-DAY Y-90 DAUGHTER. 10712 2 16 ((9.)38-SR-91,9.48HR,DG,555.63,0.58,DG,749.77,0.24, 10712 2 17 DG,1024.25,0.33) 10712 2 18 ((10.)39-Y-91-G,58.51D,B) 10712 2 19 ((11.)38-SR-92,2.71HR,DG,1383.94,0.90) 10712 2 20 ((12.)39-Y-92,3.53HR,DG,934.52,0.137) 10712 2 21 ((13.)39-Y-93,10.24HR,DG,266.87,0.068,DG,947.10,0.0194,10712 2 22 DG,1917.8,0.014) 10712 2 23 ((14.)40-ZR-95,65.0D,B,,,DG,756.72,0.546, 10712 2 24 DG,765.80,0.990) 10712 2 25 ((15.)41-NB-96,23.4HR,DG,568.86,0.558,DG,778.82,0.968, 10712 2 26 DG,1091.31,0.495) 10712 2 27 ((16.)40-ZR-97,16.82HR,B,,,DG,658.18,0.990, 10712 2 28 DG,743.37,0.940) 10712 2 29 ((17.)42-MO-99,2.752D,B,,,DG,140.514,0.805, 10712 2 30 DG,181.092,0.0604, 10712 2 31 DG,739.481,0.120, 10712 2 32 DG,777.900,0.0424) 10712 2 33 ((18.)44-RU-103,39.6D,DG,497.09,0.900) 10712 2 34 ((19.)44-RU-105,4.44HR,DG,469.38,0.175,DG,676.40,0.167)10712 2 35 ((20.)45-RH-105-G,1.476D,DG,319.24,0.196) 10712 2 36 ((21.)44-RU-106,369.D,DG,622.10,0.098) 10712 2 37 ((22.)46-PD-109-G,13.47HR,DG,88.04,0.0379) 10712 2 38 ((23.)47-AG-110-M,260.D,DG,937.3,0.336,DG,1384.3,0.24) 10712 2 39 ((24.)46-PD-111-M,5.5HR,DG,172.2,0.324) 10712 2 40 ((25.)47-AG-111-G,7.431D,B,,,DG,342.14,0.0668) 10712 2 41 ((26.)46-PD-112,21.12HR,DG,617.40,0.435) 10712 2 42 ((27.)47-AG-113-G,5.371HR,B,,,DG,298.4,0.093) 10712 2 43 ((28.)48-CD-115-G,2.208D,B,,,DG,336.26,0.465, 10712 2 44 DG,492.29,0.0826, 10712 2 45 DG,527.86,0.280) 10712 2 46 ((29.)48-CD-115-M,44.6D,B) 10712 2 47 ((30.)48-CD-117-G,2.56HR,DG,273.31,0.284, 10712 2 48 DG,344.51,0.173, 10712 2 49 DG,1303.4,0.176) 10712 2 50 ((31.)48-CD-117-M,3.35HR,DG,564.4,0.153, 10712 2 51 DG,1066.0,0.231, 10712 2 52 DG,1997.4,0.254) 10712 2 53 ((32.)48-CD-118,0.838HR,DG,1229.5,0.15) 10712 2 54 ((33.)50-SN-125-G,9.65D,DG,822.6,0.0387, 10712 2 55 DG,915.5,0.0376, 10712 2 56 DG,1066.6,0.0887) 10712 2 57 ((34.)51-SB-125,2.77YR,DG,427.88,0.304) 10712 2 58 ((35.)51-SB-126-G,12.5D,DG,414.7,0.810,DG,666.2,1.00, 10712 2 59 DG,695.1,1.00) 10712 2 60 ((36.)50-SN-127-G,2.12HR,DG,1095.6,0.195) 10712 2 61 ((37.)51-SB-127,3.87D,DG,473.20,0.248,DG,684.90,0.368) 10712 2 62 ((38.)50-SN-128,1.00HR,DG,482.0,0.66) 10712 2 63 ((39.)51-SB-128-G,9.01HR,DG,636.2,0.360) 10712 2 64 ((40.)51-SB-129,4.32HR,DG,544.7,0.181,DG,914.6,0.202, 10712 2 65 DG,1030.1,0.127) 10712 2 66 ((41.)51-SB-130-G,0.667HR,DG,330.9,0.78,DG,839.4,1.00) 10712 2 67 ((42.)53-I-130-G,12.36HR,DG,536.09,0.99) 10712 2 68 ((43.)52-TE-131-M,1.25D,DG,793.80,0.159, 10712 2 69 DG,852.30,0.256, 10712 2 70 DG,1125.30,0.148, 10712 2 71 DG,1206.6,0.118) 10712 2 72 ((44.)53-I-131,8.022D,DG,364.46,0.79) 10712 2 73 ((45.)52-TE-132,3.24D,DG,228.2,0.88,DG,522.60,0.156, 10712 2 74 DG,630.20,0.135) 10712 2 75 ((46.)55-CS-132,6.475D,DG,667.5,0.974) 10712 2 76 ((47.)53-I-133-G,21.0HR,DG,529.91,0.83) 10712 2 77 ((48.)55-CS-134-G,767.D,DG,604.70,0.98) 10712 2 78 ((49.)55-CS-134-M,2.90HR,DG,127.42,0.143) 10712 2 79 ((50.)53-I-135,6.610HR,DG,1260.41,0.284, 10712 2 80 DG,1457.56,0.0858, 10712 2 81 DG,1678.03,0.0947) 10712 2 82 ((51.)54-XE-135-G,9.106HR,DG,249.65,0.92) 10712 2 83 ((52.)55-CS-135-G,2.3E+06YR) 10712 2 84 ((53.)55-CS-135-M,0.883HR,DG,786.34,0.997, 10712 2 85 DG,845.05,0.959) 10712 2 86 ((54.)55-CS-136-G,13.0D,DG,818.48,1.000, 10712 2 87 DG,1048.10,0.805, 10712 2 88 DG,1235.41,0.197) 10712 2 89 ((55.)55-CS-137,30.01YR,DG,661.62,0.850) 10712 2 90 ((56.)55-CS-138-G,0.557HR,DG,462.7,0.270, 10712 2 91 DG,1009.7,0.285, 10712 2 92 DG,1435.7,0.750) 10712 2 93 ((57.)56-BA-139,1.385HR,DG,165.85,0.220) 10712 2 94 ((58.)56-BA-140,12.80D,B,,,DG,537.261,0.2446, 10712 2 95 DG,1596.20,0.9552) 10712 2 96 ((59.)58-CE-141,32.38D,B,,,DG,145.44,0.493) 10712 2 97 ((60.)57-LA-142,1.545HR,DG,641.21,0.465, 10712 2 98 DG,2398.0,0.117, 10712 2 99 DG,2542.9,0.088) 10712 2 100 ((61.)58-CE-143,1.379D,DG,293.20,0.435) 10712 2 101 ((62.)58-CE-144,284.6D,B,,,DG,133.50,0.110) 10712 2 102 ((63.)59-PR-145,5.98HR,DG,674.0,0.0043,DG,748.0,0.0043)10712 2 103 ((64.)60-ND-147,11.04D,B,,,DG,531.00,0.1295) 10712 2 104 ((65.)60-ND-149,1.721HR,DG,114.321,0.161, 10712 2 105 DG,211.307,0.234) 10712 2 106 ((66.)61-PM-149,2.208D,DG,285.90,0.031) 10712 2 107 ((67.)61-PM-151,1.183D,DG,167.73/168.38,0.092, 10712 2 108 DG,240.08,0.036,DG,340.08,0.224)10712 2 109 ((68.)62-SM-153,1.928D,B,,,DG,103.17,0.284) 10712 2 110 ((69.)63-EU-155,4.68YR,DG,86.55,0.335,DG,105.32,0.224) 10712 2 111 ((70.)63-EU-156,15.19D,B) 10712 2 112 ((71.)63-EU-157,15.15HR,B,,,DG,413.,0.186) 10712 2 113 ((72.)64-GD-159,18.56HR,B,,,DG,363.56,0.103) 10712 2 114 ((73.)65-TB-160,72.1D,B) 10712 2 115 ((74.)65-TB-161,6.91D,B) 10712 2 116 ((75.)68-ER-169,9.40D,B) 10712 2 117 COMMENT YIELD FOR I-130 GIVEN AS CORRECTED BY D.R.NETHAWAY, 10712 2 118 78/2/17. 10712 2 119 HISTORY (801028U) REMOVED MONITOR. 10712 2 120 (810309A) DATA FOR SR-88,PD-111-M AND SM-153 CORRECTED 10712 2 121 AS PER PHYS.REV.C 20,1824 (1979). 10712 2 122 (810529A) DECAY-DATA CORRECTIONS. 10712 2 123 ENDBIB 121 10712 2 124 NOCOMMON 0 0 10712 2 125 DATA 7 75 10712 2 126 MASS ELEMENT ISOMER DECAY-FLAG DATA DATA-ERR 10712 2 127 DATA-MAX 10712 2 128 NO-DIM NO-DIM NO-DIM NO-DIM PC/FIS PER-CENT 10712 2 129 PC/FIS 10712 2 130 66. 28. 1. 6.04 -05 44. 10712 2 131 10712 2 132 67. 29. 2. 1.31 -04 35. 10712 2 133 10712 2 134 72. 30. 3. 4.47 -03 10. 10712 2 135 10712 2 136 73. 31. 4. 8.34 -03 5.8 10712 2 137 10712 2 138 87. 36. 5. 1.22 8.2 10712 2 139 10712 2 140 88. 36. 6. 1.39 4.9 10712 2 141 10712 2 142 89. 38. 7. 1.74 3.0 10712 2 143 10712 2 144 90. 38. 8. 1.94 3.0 10712 2 145 10712 2 146 91. 38. 9. 2.39 3.0 10712 2 147 10712 2 148 91. 39. 10. 2.49 3.0 10712 2 149 10712 2 150 92. 38. 11. 2.77 3.0 10712 2 151 10712 2 152 92. 39. 12. 2.93 4.0 10712 2 153 10712 2 154 93. 39. 13. 2.88 3.0 10712 2 155 10712 2 156 95. 40. 14. 3.68 3.0 10712 2 157 10712 2 158 96. 41. 15. 8.34 -03 3.0 10712 2 159 10712 2 160 97. 40. 16. 4.18 3.0 10712 2 161 10712 2 162 99. 42. 17. 4.85 3.0 10712 2 163 10712 2 164 103. 44. 18. 5.27 3.0 10712 2 165 10712 2 166 105. 44. 19. 5.25 3.0 10712 2 167 10712 2 168 105. 45. 20. 4.32 3.0 10712 2 169 10712 2 170 106. 44. 21. 4.00 3.0 10712 2 171 10712 2 172 109. 46. 22. 2.29 3.0 10712 2 173 10712 2 174 110. 47. 1. 23. 10712 2 175 4.9 -04 10712 2 176 111. 46. 1. 24. 4.80 -02 8.6 10712 2 177 10712 2 178 111. 47. 25. 1.66 3.0 10712 2 179 10712 2 180 112. 46. 26. 1.56 3.0 10712 2 181 10712 2 182 113. 47. 0. 27. 1.53 5.2 10712 2 183 10712 2 184 115. 48. 0. 28. 1.09 3.0 10712 2 185 10712 2 186 115. 48. 1. 29. 7.18 -02 3.0 10712 2 187 10712 2 188 117. 48. 0. 30. 6.01 -01 3.0 10712 2 189 10712 2 190 117. 48. 1. 31. 2.57 -01 3.0 10712 2 191 10712 2 192 118. 48. 32. 4.95 -01 6.0 10712 2 193 10712 2 194 125. 50. 0. 33. 8.44 -01 3.0 10712 2 195 10712 2 196 125. 51. 34. 1.57 3.0 10712 2 197 10712 2 198 126. 51. 0. 35. 3.60 -01 3.2 10712 2 199 10712 2 200 127. 50. 0. 36. 1.43 4.0 10712 2 201 10712 2 202 127. 51. 37. 1.95 3.0 10712 2 203 10712 2 204 128. 50. 38. 9.94 -01 3.0 10712 2 205 10712 2 206 128. 51. 0. 39. 1.01 3.0 10712 2 207 10712 2 208 129. 51. 40. 1.91 4.2 10712 2 209 10712 2 210 130. 51. 0. 41. 1.71 5.0 10712 2 211 10712 2 212 130. 53. 0. 42. 0.209 4.5 10712 2 213 10712 2 214 131. 52. 1. 43. 1.54 3.0 10712 2 215 10712 2 216 131. 53. 44. 4.45 3.2 10712 2 217 10712 2 218 132. 52. 45. 3.55 3.0 10712 2 219 10712 2 220 132. 55. 46. 1.7 -03 60. 10712 2 221 10712 2 222 133. 53. 47. 5.38 3.4 10712 2 223 10712 2 224 134. 55. 0. 48. 4.22 -02 3.6 10712 2 225 10712 2 226 134. 55. 1. 49. 2.23 -02 3.8 10712 2 227 10712 2 228 135. 53. 50. 3.86 3.2 10712 2 229 10712 2 230 135. 54. 51. 5.79 6.2 10712 2 231 10712 2 232 135. 55. 0. 52. 4.97 4.1 10712 2 233 10712 2 234 135. 55. 1. 53. 6.55 -02 3.3 10712 2 235 10712 2 236 136. 55. 54. 5.03 -01 3.0 10712 2 237 10712 2 238 137. 55. 55. 4.48 4.0 10712 2 239 10712 2 240 138. 55. 56. 5.19 10. 10712 2 241 10712 2 242 139. 56. 57. 4.56 3.0 10712 2 243 10712 2 244 140. 56. 58. 3.77 3.0 10712 2 245 10712 2 246 141. 58. 59. 3.57 3.0 10712 2 247 10712 2 248 142. 57. 60. 3.88 8.0 10712 2 249 10712 2 250 143. 58. 61. 3.09 3.0 10712 2 251 10712 2 252 144. 58. 62. 2.65 3.0 10712 2 253 10712 2 254 145. 59. 63. 2.69 10. 10712 2 255 10712 2 256 147. 60. 64. 1.78 3.0 10712 2 257 10712 2 258 149. 60. 65. 1.45 3.2 10712 2 259 10712 2 260 149. 61. 66. 1.29 3.0 10712 2 261 10712 2 262 151. 61. 67. 8.05 -01 6.2 10712 2 263 10712 2 264 153. 62. 68. 5.80 -01 3.0 10712 2 265 10712 2 266 155. 63. 69. 2.78 -01 3.0 10712 2 267 10712 2 268 156. 63. 70. 2.25 -01 3.0 10712 2 269 10712 2 270 157. 63. 71. 1.58 -01 3.0 10712 2 271 10712 2 272 159. 64. 72. 6.8 -02 15. 10712 2 273 10712 2 274 160. 65. 73. 10712 2 275 1.5 -04 10712 2 276 161. 65. 74. 3.46 -02 3.0 10712 2 277 10712 2 278 169. 68. 75. 1.15 -03 4.0 10712 2 279 10712 2 280 ENDDATA 154 10712 2 281 ENDSUBENT 7 10712 299999 ENDENTRY 2 1071299999999 ENTRY 10864 900529 10864 0 1 SUBENT 10864001 900529 10864 1 1 BIB 12 16 10864 1 2 INSTITUTE (1CANMCM) 10864 1 3 REFERENCE (J,CJP,56,1340,7810) 10864 1 4 AUTHOR (M.SHIMA,H.G.THODE,R.H.TOMLINSON) 10864 1 5 TITLE CUMULATIVE YIELDS OF STABLE AND LONG-LIVED ISOTOPES OF 10864 1 6 RUTHENIUM AND PALLADIUM IN NEUTRON-INDUCED FISSION 10864 1 7 FACILITY (REAC) MC MASTER NUCLEAR REACTOR 10864 1 8 SAMPLE SAMPLE SEALED IN SMALL QUARTZ CAPSULE, WRAPPED IN 10864 1 9 ALUMINUM FOIL, AND PLACED IN ALUMINUM CAPSULES. 10864 1 10 METHOD (ASEP) ISOTOPE DILUTION MASS SPECTROMETRY. 10864 1 11 DETECTOR 15-INCH RADIUS TANDEM MASS SPECTROMETER WITH COLD TRAP 10864 1 12 ON SOURCE HEAD TO REDUCE HYDROCARBON PEAKS. 10864 1 13 ANALYSIS DATA VALUES AVERAGED OVER SEVERAL SAMPLES 10864 1 14 CORRECTION CORRECTED FOR CONTAMINATION BY NATURAL RU,PD,CD, AND AG10864 1 15 STATUS NO REPLY FROM AUTHOR. 10864 1 16 HISTORY (791218C) 10864 1 17 (900529A) BIB UPDATE, SPECTRUM CORRECTED 10864 1 18 ENDBIB 16 10864 1 19 NOCOMMON 0 0 10864 1 20 ENDSUBENT 0 10864 199999 SUBENT 10864010 900529 10864 10 1 BIB 4 5 10864 10 2 REACTION ((92-U-235(N,F)ELEM/MASS,CUM,FY,,EPI)/ 10864 10 3 (92-U-235(N,F)44-RU-101,CUM,FY,,EPI)) 10864 10 4 INC-SPECT EPICADMIUM SPECTRUM 10864 10 5 ERR-ANALYS NO INFORMATION 10864 10 6 HISTORY (900529C) 10864 10 7 ENDBIB 5 10864 10 8 COMMON 1 3 10864 10 9 EN-MIN 10864 10 10 EV 10864 10 11 0.5 10864 10 12 ENDCOMMON 1 3 10864 10 13 DATA 4 7 10864 10 14 ELEMENT MASS DATA DATA-ERR 10864 10 15 NO-DIM NO-DIM NO-DIM NO-DIM 10864 10 16 44. 102. 0.920 0.018 10864 10 17 44. 104. 0.628 0.016 10864 10 18 44. 106. 0.158 0.007 10864 10 19 46. 105. 0.235 0.006 10864 10 20 46. 107. 0.055 0.004 10864 10 21 46. 108. 0.040 0.002 10864 10 22 46. 110. 0.0135 0.0010 10864 10 23 ENDDATA 9 10864 10 24 ENDSUBENT 4 10864 1099999 SUBENT 10864011 900529 10864 11 1 BIB 4 5 10864 11 2 REACTION ((94-PU-239(N,F)ELEM/MASS,CUM,FY,,EPI)/ 10864 11 3 (94-PU-239(N,F)44-RU-101,CUM,FY,,EPI)) 10864 11 4 INC-SPECT EPICADMIUM SPECTRUM 10864 11 5 ERR-ANALYS NO INFORMATION 10864 11 6 HISTORY (900529C) 10864 11 7 ENDBIB 5 10864 11 8 COMMON 1 3 10864 11 9 EN-MIN 10864 11 10 EV 10864 11 11 0.5 10864 11 12 ENDCOMMON 1 3 10864 11 13 DATA 4 7 10864 11 14 ELEMENT MASS DATA DATA-ERR 10864 11 15 NO-DIM NO-DIM NO-DIM NO-DIM 10864 11 16 44. 102. 1.064 0.008 10864 11 17 44. 104. 1.010 0.005 10864 11 18 44. 106. 0.641 0.010 10864 11 19 46. 105. 0.90 0.05 10864 11 20 46. 107. 0.42 0.10 10864 11 21 46. 108. 0.23 0.09 10864 11 22 46. 110. 0.08 0.04 10864 11 23 ENDDATA 9 10864 11 24 ENDSUBENT 4 10864 1199999 ENDENTRY 3 1086499999999 ENTRY 10913 891113 10913 0 1 SUBENT 10913001 881113 10913 1 1 BIB 14 43 10913 1 2 INSTITUTE (1USALRL) 10913 1 3 REFERENCE (J,PR/C,20,1824,7911) 10913 1 4 AUTHOR (A.L.PRINDLE,D.H.SISSON,D.R.NETHAWAY,M.V.KANTELO, 10913 1 5 R.A.SIGG) 10913 1 6 TITLE FISSION OF AM-241 WITH 14.8-MEV NEUTRONS 10913 1 7 FACILITY (ICTR) ISOLATED CORE TRANSFORMER ACCELERATOR 10913 1 8 INC-SOURCE (D-T) 400-KEV DEUTERONS INCIDENT ON ROTATING TITANIUM 10913 1 9 TRITIDE TARGET 10913 1 10 SAMPLE TWO SAMPLE ASSEMBLIES USED- 10913 1 11 -RADIOCHEMICAL METHOD-2.5 MILLI-GRMS AM-241 AS 10913 1 12 AMERICIUM TRINITRATE, COLD WELDED BETWEEN TWO SHEETS 10913 1 13 OF ALUMINUM, WITH OR WITHOUT U-238 MONITOR FOILS. 10913 1 14 -FISSION RECOIL METHOD- FISSION FOILS OF 100 MICRO 10913 1 15 GRAMS PER SQ-CM AM-241 WITHIN A DIAMETER OF 9.5-MM 10913 1 16 PLATED ONTO PLATINUM DISKS. CATCHER FOILS OF BE 10913 1 17 SEPERATED FROM FISSION FOILS BY STAINLESS STEEL 10913 1 18 SPACERS. 10913 1 19 BOTH ASSEMBLIES SEALED INSIDE COPPER CANS AND PLACED IN10913 1 20 A CADMIUM SAMPLE HOLDER 10913 1 21 METHOD TWO MEASUREMENT METHODS USED- 10913 1 22 (RCHEM) PRODUCTS SEQUENTIALLY SEPARATED FROM 10913 1 23 IRRADIATED AM-241 SAMPLE. GAMMA AND BETA COUNTING 10913 1 24 TECHNIQUES USED TO DETERMINE FISSION YIELDS. 10913 1 25 (GSPEC) FISSION RECOIL. MEASUREMENTS MADE DIRECTLY 10913 1 26 FROM SAMPLE USING GAMMA-RAY SPECTROSCOPY. 10913 1 27 DETECTOR (GELI) GERMANIUM LITHIUM COUNTER FOR PRODUCT ANALYSIS 10913 1 28 AND TO CHECK FOR COMPLETE REMOVAL OF AM-241 AFTER 10913 1 29 IRRADIATION. 10913 1 30 PROTON RECOIL COUNTER USED AS FLUX MONITOR 10913 1 31 MONITOR (92-U-238(N,F),,SIG) 10913 1 32 YIELDS MEASURED RELATIVE TO MO-99, THEN AVERAGED OVER 10913 1 33 EACH RUN. FISSION YIELDS CALCULATED BY REQUIRING UNIT 10913 1 34 TOTAL YIELD IN EACH HALF OF THE MASS DISTRIBUTION. 10913 1 35 CORRECTION OBSERVED AMOUNTS OF EACH FISSION PRODUCT CORRECTED FOR 10913 1 36 GROWTH AND DECAY DURING AND AFTER IRRADIATION. 10913 1 37 ERR-ANALYS (DATA-ERR) STANDARD DEVIATION. DOES NOT INCLUDE 10913 1 38 SYSTEMATIC UNCERTAINTY IN YIELD DETERMINATION 10913 1 39 (ESTIMATED 4%). 10913 1 40 STATUS (APRVD) APPROVED BY A.L.PRINDLE, 81/3/2. 10913 1 41 HISTORY (801125C) 10913 1 42 (820108A) MOVED DECAY-DATA TO SAN=2. 10913 1 43 (840917A) BIB CORRECTION. 10913 1 44 (891113A) BIB UPDATE. 10913 1 45 ENDBIB 43 10913 1 46 COMMON 4 3 10913 1 47 EN EN-RSL MONIT MONIT-ERR 10913 1 48 MEV MEV B B 10913 1 49 14.8 0.3 1.19 0.03 10913 1 50 ENDCOMMON 4 3 10913 1 51 ENDSUBENT 4 10913 199999 SUBENT 10913002 840917 10913 2 1 BIB 3 75 10913 2 2 REACTION (95-AM-241(N,F)ELEM/MASS,CUM,FY) 10913 2 3 DECAY-DATA ((1.)37-RB-86-G,18.66D,DG,1076.6,0.0878) 10913 2 4 ((2.)36-KR-87,1.267HR,DG,402.47,0.473, 10913 2 5 DG,2554.92,0.0847) 10913 2 6 ((3.)36-KR-88,2.803HR,DG,196.1,0.288) 10913 2 7 ((4.)38-SR-91,9.48HR,DG,555.63,0.58,DG,749.77,0.24, 10913 2 8 DG,1024.25,0.33) 10913 2 9 ((5.)39-Y-91-G,58.51D,B) 10913 2 10 ((6.)38-SR-92,2.71HR,DG,1383.94,0.90) 10913 2 11 ((7.)39-Y-94,19.1MIN,DG,918.24,0.56) 10913 2 12 ((8.)40-ZR-95,65.0D,B) 10913 2 13 ((9.)41-NB-96,23.4HR,DG,568.86,0.558,DG,778.22,0.968) 10913 2 14 ((10.)40-ZR-97,16.82HR,B) 10913 2 15 ((11.)42-MO-99,2.752D,DG,140.514,0.805, 10913 2 16 DG,181.092,0.0604,DG,739.481,0.120,DG,777.900,0.0424, 10913 2 17 B) 10913 2 18 ((12.)44-RU-103,39.6D,DG,497.09,0.900) 10913 2 19 ((13.)43-TC-104,18.2MIN,DG,357.99,0.903) 10913 2 20 ((14.)45-RH-105-G,1.476D,DG,319.24,0.196) 10913 2 21 ((15.)44-RU-106,369.D,DG,622.10,0.098) 10913 2 22 ((16.)45-RH-107,21.7MIN,DG,302.8,0.66) 10913 2 23 ((17.)46-PD-109-G,13.47HR,DG,88.04,0.0379) 10913 2 24 ((18.)47-AG-110-M,260.D,DG,937.3,0.336,DG,1384.3,0.24) 10913 2 25 ((19.)46-PD-111-M,5.5HR,DG,172.2,0.324) 10913 2 26 ((20.)47-AG-111-G,7.431D,DG,342.14,0.0668,B) 10913 2 27 ((21.)46-PD-112,21.12HR,DG,617.40,0.435) 10913 2 28 ((22.)47-AG-113-G,5.371HR,DG,298.4,0.093,B) 10913 2 29 ((23.)48-CD-115-G,2.208D,DG,336.25,0.465, 10913 2 30 DG,492.29,0.0826,DG,527.86,0.280,B) 10913 2 31 ((24.)48-CD-115-M,3.35HR,DG,564.4,0.153, 10913 2 32 DG,1066.0,0.231,DG,1997.4,0.254) 10913 2 33 ((25.)51-SB-126-G,12.5D,DG,414.7,0.810,DG,666.2,1.00, 10913 2 34 DG,695.1,1.00) 10913 2 35 ((26.)51-SB-127,3.87D,DG,473.20,0.248,DG,684.90,0.368) 10913 2 36 ((27.)50-SN-128,1.00HR,DG,482.0,0.66) 10913 2 37 ((28.)51-SB-128-G,9.01HR,DG,636.2,0.360) 10913 2 38 ((29.)53-I-130-G,12.36HR,DG,536.09,0.99) 10913 2 39 ((30.)52-TE-131-M,1.25D,DG,793.80,0.159, 10913 2 40 DG,852.30,0.256,DG,1125.50,0.148,DG,1206.6,0.118) 10913 2 41 ((31.)53-I-131,8.022D,DG,364.46,0.79) 10913 2 42 ((32.)52-TE-132,3.24D,DG,228.2,0.88,DG,522.60,0.156, 10913 2 43 DG,630.20,0.135) 10913 2 44 ((33.)55-CS-132,6.475D,DG,667.5,0.974) 10913 2 45 ((34.)53-I-133-G,21.0HR,DG,529.91,0.83) 10913 2 46 ((35.)54-XE-133-G,5.227D,DG,81.00,0.364) 10913 2 47 ((36.)55-CS-134-G,767.D,DG,604.70,0.98) 10913 2 48 ((37.)53-I-135,6.610HR,DG,1260.41,0.284, 10913 2 49 DG,1457.56,0.0858,DG,1678.03,0.0947) 10913 2 50 ((38.)54-XE-135-G,9.106HR,DG,249.65,0.92) 10913 2 51 ((39.)55-CS-136-G,13.0D,DG,818.48,1.000, 10913 2 52 DG,1048.10,0.805,DG,1235.41,0.197) 10913 2 53 ((40.)55-CS-137,30.01YR,DG,661.62,0.850) 10913 2 54 ((41.)56-BA-139,1.385HR,DG,165.85,0.220) 10913 2 55 ((42.)56-BA-140,12.80D,DG,537.261,0.2446, 10913 2 56 DG,1596.20,0.9552,B) 10913 2 57 ((43.)58-CE-141,32.38D,DG,145.44,0.493,B) 10913 2 58 ((44.)57-LA-142,1.545HR,DG,641.21,0.465, 10913 2 59 DG,2398.0,0.117,DG,2542.9,0.088) 10913 2 60 ((45.)58-CE-143,1.379D,DG,293.20,0.435) 10913 2 61 ((46.)58-CE-144,284.6D,DG,133.50,0.110,B) 10913 2 62 ((47.)60-ND-147,11.04D,DG,531.00,0.1295,B) 10913 2 63 ((48.)61-PM-149,2.208D,DG,285.90,0.031) 10913 2 64 ((49.)61-PM-151,1.183D,DG,167.73,0.092, 10913 2 65 DG,168.38,0.092,DG,240.08,0.036,DG,340.08,0.224) 10913 2 66 ((50.)62-SM-153,1.928D,DG,103.17,0.284,B) 10913 2 67 ((51.)63-EU-155,4.68YR,DG,86.55,0.335,DG,105.32,0.224) 10913 2 68 ((52.)62-SM-156,9.4HR,DG,203.8,0.24) 10913 2 69 ((53.)63-EU-156,15.19D,B) 10913 2 70 ((54.)63-EU-157,15.15HR,DG,413.,0.186,B) 10913 2 71 ((55.)64-GD-159,18.56HR,DG,363.56,0.103,B) 10913 2 72 ((56.)65-TB-160,72.1D,B) 10913 2 73 ((57.)65-TB-161,6.91D,B) 10913 2 74 HISTORY (820108A) DECAY-DATA MOVED FROM SAN=1. 10913 2 75 (821203U) DECAY DATA CORRECTED. 10913 2 76 (840917A) DECAY DATA CORRECTED. 10913 2 77 ENDBIB 75 10913 2 78 NOCOMMON 0 0 10913 2 79 DATA 7 57 10913 2 80 ELEMENT MASS ISOMER DATA-MAX DATA DATA-ERR 10913 2 81 DECAY-FLAG 10913 2 82 NO-DIM NO-DIM NO-DIM PC/FIS PC/FIS PER-CENT 10913 2 83 NO-DIM 10913 2 84 36. 87. 0.0105 4.1 10913 2 85 2. 10913 2 86 36. 88. 0.0107 3.0 10913 2 87 3. 10913 2 88 37. 86. 1.9 E-05 10913 2 89 1. 10913 2 90 38. 91. 0.0201 3.1 10913 2 91 4. 10913 2 92 38. 92. 0.0215 3.0 10913 2 93 6. 10913 2 94 39. 91. 0.0208 3.0 10913 2 95 5. 10913 2 96 39. 94. 0.0255 3.0 10913 2 97 7. 10913 2 98 40. 95. 0.0314 3.0 10913 2 99 8. 10913 2 100 40. 97. 0.0339 3.0 10913 2 101 10. 10913 2 102 41. 96. 1.57 E-04 3.0 10913 2 103 9. 10913 2 104 42. 99. 0.0436 3.0 10913 2 105 11. 10913 2 106 43. 104. 0.0463 3.0 10913 2 107 13. 10913 2 108 44. 103. 0.0507 3.0 10913 2 109 12. 10913 2 110 44. 106. 0.0410 3.0 10913 2 111 15. 10913 2 112 45. 105. 0.0476 3.0 10913 2 113 14. 10913 2 114 45. 107. 0.0380 3.0 10913 2 115 16. 10913 2 116 46. 109. 0.0324 3.0 10913 2 117 17. 10913 2 118 46. 111. 1. 1.77 E-03 8.4 10913 2 119 19. 10913 2 120 46. 112. 0.0242 3.0 10913 2 121 21. 10913 2 122 47. 110. 1. 3.5 E-05 10913 2 123 18. 10913 2 124 47. 111. 0.0231 3.0 10913 2 125 20. 10913 2 126 47. 113. 0.0221 3.0 10913 2 127 22. 10913 2 128 48. 115. 0. 0.0160 3.0 10913 2 129 23. 10913 2 130 48. 115. 1. 1.30 E-03 3.0 10913 2 131 24. 10913 2 132 50. 128. 4.93 E-03 3.0 10913 2 133 27. 10913 2 134 51. 126. 0. 6.89 E-03 12.4 10913 2 135 25. 10913 2 136 51. 127. 0.0223 4.6 10913 2 137 26. 10913 2 138 51. 128. 0. 0.0117 3.0 10913 2 139 28. 10913 2 140 52. 131. 1. 0.0140 7.1 10913 2 141 30. 10913 2 142 52. 132. 0.0216 3.0 10913 2 143 32. 10913 2 144 53. 130. 0. 6.67 E-03 4.0 10913 2 145 29. 10913 2 146 53. 131. 0.0445 3.0 10913 2 147 31. 10913 2 148 53. 133. 0.0430 3.0 10913 2 149 34. 10913 2 150 53. 135. 0.0181 4.1 10913 2 151 37. 10913 2 152 54. 133. 0.0460 3.0 10913 2 153 35. 10913 2 154 54. 135. 0.0449 3.0 10913 2 155 38. 10913 2 156 55. 132. 7.85 E-05 13.4 10913 2 157 33. 10913 2 158 55. 134. 0. 2.25 E-03 4.9 10913 2 159 36. 10913 2 160 55. 136. 0.0124 3.0 10913 2 161 39. 10913 2 162 55. 137. 0.0425 3.0 10913 2 163 40. 10913 2 164 56. 139. 0.0402 3.0 10913 2 165 41. 10913 2 166 56. 140. 0.0334 3.0 10913 2 167 42. 10913 2 168 57. 142. 0.0296 3.3 10913 2 169 44. 10913 2 170 58. 141. 0.0323 3.0 10913 2 171 43. 10913 2 172 58. 143. 0.0269 3.0 10913 2 173 45. 10913 2 174 58. 144. 0.0249 3.0 10913 2 175 46. 10913 2 176 60. 147. 0.0181 3.0 10913 2 177 47. 10913 2 178 61. 149. 0.0130 3.0 10913 2 179 48. 10913 2 180 61. 151. 8.85 E-03 3.0 10913 2 181 49. 10913 2 182 62. 153. 6.68 E-03 3.0 10913 2 183 50. 10913 2 184 62. 156. 2.20 E-03 4.9 10913 2 185 52. 10913 2 186 63. 155. 3.39 E-03 3.0 10913 2 187 51. 10913 2 188 63. 156. 2.70 E-03 3.0 10913 2 189 53. 10913 2 190 63. 157. 1.69 E-03 3.0 10913 2 191 54. 10913 2 192 64. 159. 1.31 E-03 4.2 10913 2 193 55. 10913 2 194 65. 160. 2.92 E-05 5.1 10913 2 195 56. 10913 2 196 65. 161. 6.01 E-04 3.0 10913 2 197 57. 10913 2 198 ENDDATA 118 10913 2 199 ENDSUBENT 7 10913 299999 SUBENT 10913003 810112 10913 3 1 BIB 2 2 10913 3 2 REACTION (95-AM-241(N,F)MASS,CHN,FY) 10913 3 3 STATUS (DEP,10913002) 10913 3 4 ENDBIB 2 10913 3 5 NOCOMMON 0 0 10913 3 6 DATA 3 38 10913 3 7 MASS DATA DATA-ERR 10913 3 8 NO-DIM PC/FIS PC/FIS 10913 3 9 87. 0.0109 0.0005 10913 3 10 88. 0.0119 0.0005 10913 3 11 91. 0.0206 0.0006 10913 3 12 92. 0.0223 0.0007 10913 3 13 94. 0.0258 0.0008 10913 3 14 95. 0.0314 0.0009 10913 3 15 97. 0.0350 0.0011 10913 3 16 99. 0.0436 0.0013 10913 3 17 103. 0.0507 0.0015 10913 3 18 104. 0.0466 0.0014 10913 3 19 105. 0.0476 0.0014 10913 3 20 106. 0.0411 0.0012 10913 3 21 107. 0.0380 0.0011 10913 3 22 109. 0.0324 0.0010 10913 3 23 111. 0.0231 0.0007 10913 3 24 112. 0.0254 0.0012 10913 3 25 113. 0.0222 0.0007 10913 3 26 115. 0.0173 0.0005 10913 3 27 127. 0.0233 0.0012 10913 3 28 131. 0.0447 0.0013 10913 3 29 133. 0.0468 0.0014 10913 3 30 135. 0.0484 0.0018 10913 3 31 137. 0.0436 0.0014 10913 3 32 139. 0.0405 0.0012 10913 3 33 140. 0.0346 0.0011 10913 3 34 141. 0.0323 0.0010 10913 3 35 142. 0.0299 0.0010 10913 3 36 143. 0.0269 0.0008 10913 3 37 144. 0.0249 0.0007 10913 3 38 147. 0.0181 0.0005 10913 3 39 149. 0.0130 0.0004 10913 3 40 151. 8.87 E-03 2.7 E-04 10913 3 41 153. 6.68 E-03 2.0 E-04 10913 3 42 155. 3.39 E-03 1.0 E-04 10913 3 43 156. 2.65 E-03 8.0 E-05 10913 3 44 157. 1.70 E-03 5.0 E-05 10913 3 45 159. 1.31 E-03 6.0 E-05 10913 3 46 161. 6.01 E-04 1.8 E-05 10913 3 47 ENDDATA 40 10913 3 48 ENDSUBENT 3 10913 399999 SUBENT 10913004 891113 10913 4 1 BIB 3 4 10913 4 2 REACTION ((95-AM-241(N,F)ELEM/MASS,IND,FY)/ 10913 4 3 (95-AM-241(N,F)MASS,CHN,FY)) 10913 4 4 RESULT (FRIND) 10913 4 5 HISTORY (820326A) CORRECTED REACTION. 10913 4 6 ENDBIB 4 10913 4 7 NOCOMMON 0 0 10913 4 8 DATA 6 9 10913 4 9 ELEMENT MASS ISOMER DATA-MAX DATA DATA-ERR 10913 4 10 NO-DIM NO-DIM NO-DIM NO-DIM NO-DIM NO-DIM 10913 4 11 37. 86. 0.0021 10913 4 12 41. 96. 0.00474 0.00024 10913 4 13 47. 110. 1. 0.0012 10913 4 14 51. 126. 0. 0.26 0.03 10913 4 15 53. 130. 0. 0.170 0.010 10913 4 16 55. 132. 0.0017 0.0002 10913 4 17 55. 134. 0. 0.0447 0.0028 10913 4 18 55. 136. 0.256 0.013 10913 4 19 65. 160. 0.0352 0.0018 10913 4 20 ENDDATA 11 10913 4 21 ENDSUBENT 6 10913 499999 SUBENT 10913005 891113 10913 5 1 BIB 2 3 10913 5 2 REACTION ((95-AM-241(N,F)ELEM/MASS,CUM,FY)/ 10913 5 3 (95-AM-241(N,F)MASS,CHN,FY)) 10913 5 4 RESULT (FRCUM) 10913 5 5 ENDBIB 3 10913 5 6 NOCOMMON 0 0 10913 5 7 DATA 4 3 10913 5 8 ELEMENT MASS DATA DATA-ERR 10913 5 9 NO-DIM NO-DIM NO-DIM NO-DIM 10913 5 10 50. 128. 0.152 0.008 10913 5 11 52. 132. 0.469 0.023 10913 5 12 53. 135. 0.364 0.021 10913 5 13 ENDDATA 5 10913 5 14 ENDSUBENT 4 10913 599999 ENDENTRY 5 1091399999999 ENTRY 10994 900404 10994 0 1 SUBENT 10994001 900404 10994 1 1 BIB 12 19 10994 1 2 INSTITUTE (1USALRL) 10994 1 3 REFERENCE (J,JIN,43,889,8105) 10994 1 4 AUTHOR (D.R.NETHAWAY,A.E.RICHARDSON) 10994 1 5 TITLE INDEPENDENT YIELDS OF 148M-PM, 148G-PM AND 150-PM FROM 10994 1 6 FISSION OF 235-U AND 238-U WITH 14.8 MEV NEUTRONS. 10994 1 7 FACILITY (ICTR) 10994 1 8 INC-SOURCE (D-T) DEUTERONS ON ROTATING TI-T TARGET. 10994 1 9 METHOD (RCHEM) PM ISOTOPES SEPARATED FROM OTHER RADIO-ISOTOPES10994 1 10 BY CHEMICAL SEPARATION. 10994 1 11 PROGRAM GAMANAL USED TO ANALYZE DATA. 10994 1 12 DETECTOR (GELI) 10994 1 13 FLUX MONITORED WITH PROTON-RECOIL COUNTER. 10994 1 14 MONITOR YIELDS OF 148M-PM,148G-PM AND 150-PM MEASURED 10994 1 15 RELATIVE TO YIELDS OF 147-MO,149-PM AND 151-PM. 10994 1 16 CORRECTION CORRECTED FOR CHEMICAL YIELD AND DECAY BACK TO END OF 10994 1 17 IRRADIATION. 10994 1 18 STATUS (APRVD) APPROVED BY D.R.NETHAWAY, 81/11/13. 10994 1 19 HISTORY (810913C) 10994 1 20 (900404A) BIB UPDATE. 10994 1 21 ENDBIB 19 10994 1 22 COMMON 2 3 10994 1 23 EN EN-RSL 10994 1 24 MEV MEV 10994 1 25 14.8 0.3 10994 1 26 ENDCOMMON 2 3 10994 1 27 ENDSUBENT 2 10994 199999 SUBENT 10994002 811005 10994 2 1 BIB 5 17 10994 2 2 REACTION (92-U-235(N,F)ELEM/MASS,IND,FY,,RAW) 10994 2 3 TOTAL NUMBER OF ATOMS FORMED 10994 2 4 DECAY-DATA ((1.)60-ND-147,11.04D,DG,91.1,0.278,DG,531.0,0.1295) 10994 2 5 ((2.)61-PM-148-M,41.3D,DG,550.1,0.928,DG,629.9,0.892, 10994 2 6 DG,725.6,0.328,DG,1013.7,0.204) 10994 2 7 ((3.)61-PM-149,53.08HR,DG,285.9,0.031) 10994 2 8 ((4.)61-PM-150,2.68HR,DG,1165.8,0.170,DG,1324.5,0.188) 10994 2 9 ((5.)61-PM-151,28.40HR,DG,340.1,0.224) 10994 2 10 MISC-COL (MISC) EXPERIMENT NUMBER. 10994 2 11 CORRECTION CORRECTED FOR THE 5.2 PERCENT 238-U IN SAMPLE AND 10994 2 12 FOR FISSION OF OTHER URANIUM ISOTOPES. 10994 2 13 ERR-ANALYS 1-SIGMA ERROR GIVEN INCLUDES 10994 2 14 - UNCERTAINTIES IN GAMMA-RAY MEASUREMENT 10994 2 15 - PHOTON ABUNDANCES 10994 2 16 - DETECTOR EFFICIENCY 10994 2 17 - GAMMA-RAY SUMMING CORRECTIONS 10994 2 18 - UNCERTAINTY IN TOTAL CHAIN YIELDS 10994 2 19 ENDBIB 17 10994 2 20 NOCOMMON 0 0 10994 2 21 DATA 7 13 10994 2 22 ELEMENT MASS ISOMER DATA DATA-ERR DECAY-FLAG 10994 2 23 MISC 10994 2 24 NO-DIM NO-DIM NO-DIM ARB-UNITS ARB-UNITS NO-DIM 10994 2 25 NO-DIM 10994 2 26 60. 147. 5.97 +11 0.04 +11 1. 10994 2 27 1. 10994 2 28 60. 147. 2.96 +11 0.02 +11 1. 10994 2 29 2. 10994 2 30 60. 147. 5.08 +12 0.03 +12 1. 10994 2 31 3. 10994 2 32 61. 148. 1. 2.92 +07 0.09 +07 2. 10994 2 33 3. 10994 2 34 61. 148. 0. 3.82 +06 0.38 +06 10994 2 35 3. 10994 2 36 61. 149. 3.08 +11 0.08 +11 3. 10994 2 37 1. 10994 2 38 61. 149. 1.52 +11 0.03 +11 3. 10994 2 39 2. 10994 2 40 61. 149. 2.42 +12 0.05 +12 3. 10994 2 41 3. 10994 2 42 61. 150. 3.97 +08 0.16 +08 4. 10994 2 43 1. 10994 2 44 61. 150. 1.93 +08 0.09 +08 4. 10994 2 45 2. 10994 2 46 61. 151. 1.60 +11 0.01 +11 5. 10994 2 47 1. 10994 2 48 61. 151. 8.05 +10 0.06 +10 5. 10994 2 49 2. 10994 2 50 61. 151. 1.31 +12 0.01 +12 5. 10994 2 51 3. 10994 2 52 ENDDATA 30 10994 2 53 ENDSUBENT 7 10994 299999 SUBENT 10994003 811005 10994 3 1 BIB 5 17 10994 3 2 REACTION (92-U-238(N,F)ELEM/MASS,IND,FY,,RAW) 10994 3 3 TOTAL NUMBER OF ATOMS FORMED. 10994 3 4 DECAY-DATA ((1.)60-ND-147,11.04D,DG,91.1,0.278,DG,531.0,0.1295) 10994 3 5 ((2.)61-PM-148-M,41.3D,DG,550.1,0.928,DG,629.9,0.892, 10994 3 6 DG,725.6,0.328,DG,1013.7,0.204) 10994 3 7 ((3.)61-PM-149,53.08HR,DG,285.9,0.031) 10994 3 8 ((4.)61-PM-150,2.68HR,DG,1165.8,0.170,DG,1324.5,0.188) 10994 3 9 ((5.)61-PM-151,28.40HR,DG,340.1,0.224) 10994 3 10 MISC-COL (MISC) EXPERIMENT NUMBER. 10994 3 11 CORRECTION CORRECTED FOR THE 0.0483 PERCENT 235-U IN SAMPLE AND 10994 3 12 FOR FISSION OF OTHER URANIUM ISOTOPES. 10994 3 13 ERR-ANALYS 1-SIGMA ERROR GIVEN INCLUDES 10994 3 14 - UNCERTAINTIES IN GAMMA-RAY MEASUREMENTS 10994 3 15 - PHOTON ABUNDANCES 10994 3 16 - DETECTOR EFFICIENCY 10994 3 17 - GAMMA-RAY SUMMING CORRECTIONS 10994 3 18 - UNCERTAINTY IN TOTAL CHAIN YIELDS 10994 3 19 ENDBIB 17 10994 3 20 NOCOMMON 0 0 10994 3 21 DATA 8 13 10994 3 22 ELEMENT MASS ISOMER DATA DATA-ERR DATA-MAX 10994 3 23 DECAY-FLAG MISC 10994 3 24 NO-DIM NO-DIM NO-DIM ARB-UNITS ARB-UNITS ARB-UNITS 10994 3 25 NO-DIM NO-DIM 10994 3 26 60. 147. 3.15 +11 0.02 +11 10994 3 27 1. 1. 10994 3 28 60. 147. 1.85 +11 0.01 +11 10994 3 29 1. 2. 10994 3 30 60. 147. 2.62 +12 0.02 +12 10994 3 31 1. 3. 10994 3 32 61. 148. 1. 3.3 +0510994 3 33 2. 3. 10994 3 34 61. 148. 0. 2.7 +0510994 3 35 3. 10994 3 36 61. 149. 1.84 +11 0.05 +11 10994 3 37 3. 1. 10994 3 38 61. 149. 1.12 +11 0.02 +11 10994 3 39 3. 2. 10994 3 40 61. 149. 1.53 +12 0.03 +12 10994 3 41 3. 3. 10994 3 42 61. 150. 2.0 +06 1.7 +06 10994 3 43 4. 1. 10994 3 44 61. 150. 2.1 +06 0.6 +06 10994 3 45 4. 2. 10994 3 46 61. 151. 9.95 +10 0.08 +10 10994 3 47 5. 1. 10994 3 48 61. 151. 6.05 +10 0.04 +10 10994 3 49 5. 2. 10994 3 50 61. 151. 8.43 +11 0.04 +11 10994 3 51 5. 3. 10994 3 52 ENDDATA 30 10994 3 53 ENDSUBENT 8 10994 399999 SUBENT 10994004 900404 10994 4 1 BIB 5 8 10994 4 2 REACTION ((92-U-235(N,F)MASS,CHN,FY,,REL)// 10994 4 3 (92-U-235(N,F)MASS,CHN,FY)) 10994 4 4 ANALYSIS ASSUMED YIELDS FOR 147-ND, 149-PM AND 151-PM WERE 10994 4 5 EQUAL TO TOTAL CHAIN YIELD. YIELDS FOR MASSES 148 10994 4 6 AND 150 WERE INTERPOLATED. 10994 4 7 ERR-ANALYS NO INFORMATION 10994 4 8 STATUS (DEP,10994002) 10994 4 9 HISTORY (900404A) UPDATE TO NEW FORMATS. 10994 4 10 ENDBIB 8 10994 4 11 COMMON 1 3 10994 4 12 MASS-DN 10994 4 13 NO-DIM 10994 4 14 147. 10994 4 15 ENDCOMMON 1 3 10994 4 16 DATA 3 4 10994 4 17 MASS-NM DATA DATA-ERR 10994 4 18 NO-DIM NO-DIM NO-DIM 10994 4 19 148. 0.717 0.036 10994 4 20 149. 0.498 0.013 10994 4 21 150. 0.368 0.018 10994 4 22 151. 0.264 0.004 10994 4 23 ENDDATA 6 10994 4 24 ENDSUBENT 3 10994 499999 SUBENT 10994005 900404 10994 5 1 BIB 5 8 10994 5 2 REACTION ((92-U-238(N,F)MASS,CHN,FY)// 10994 5 3 (92-U-238(N,F)MASS,CHN,FY)) 10994 5 4 ANALYSIS ASSUMED YIELDS FOR 147-ND, 149-PM AND 151-PM WERE 10994 5 5 EQUAL TO TOTAL CHAIN YIELD. YIELDS FOR MASSES 148 10994 5 6 AND 150 WERE INTERPOLATED. 10994 5 7 ERR-ANALYS NO INFORMATION 10994 5 8 STATUS (DEP,10994003) 10994 5 9 HISTORY (900404A) UPDATE TO NEW FORMATS. 10994 5 10 ENDBIB 8 10994 5 11 COMMON 1 3 10994 5 12 MASS-DN 10994 5 13 NO-DIM 10994 5 14 147. 10994 5 15 ENDCOMMON 1 3 10994 5 16 DATA 3 4 10994 5 17 MASS-NM DATA DATA-ERR 10994 5 18 NO-DIM NO-DIM NO-DIM 10994 5 19 148. 0.783 0.039 10994 5 20 149. 0.591 0.007 10994 5 21 150. 0.437 0.022 10994 5 22 151. 0.322 0.003 10994 5 23 ENDDATA 6 10994 5 24 ENDSUBENT 3 10994 599999 SUBENT 10994006 900404 10994 6 1 BIB 5 11 10994 6 2 REACTION ((92-U-235(N,F)ELEM/MASS,IND,FY)/ 10994 6 3 (92-U-235(N,F)MASS,CHN,FY)) 10994 6 4 RESULT (FRIND) 10994 6 5 ERR-ANALYS (DATA-ERR) 1-SIGMA ERRORS INCLUDE UNCERTAINTIES IN: 10994 6 6 - GAMMA-RAY MEASUREMENTS 10994 6 7 - PHOTON ABUNDANCES 10994 6 8 - DETECTOR EFFICIENCY CALIBRATION (ESTIMATED 2%) 10994 6 9 - GAMMA SUMMING CORRECTIONS 10994 6 10 - TOTAL CHAIN YIELDS (5%) 10994 6 11 STATUS (DEP,10994002) 10994 6 12 HISTORY (900404A) UPDATE. 10994 6 13 ENDBIB 11 10994 6 14 COMMON 1 3 10994 6 15 ELEMENT 10994 6 16 NO-DIM 10994 6 17 61. 10994 6 18 ENDCOMMON 1 3 10994 6 19 DATA 4 3 10994 6 20 MASS ISOMER DATA DATA-ERR 10994 6 21 NO-DIM NO-DIM NO-DIM NO-DIM 10994 6 22 148. 1. 8.0 -06 0.6 -06 10994 6 23 148. 0. 1.05 -06 0.13 -06 10994 6 24 150. 1.79 -03 0.15 -03 10994 6 25 ENDDATA 5 10994 6 26 ENDSUBENT 4 10994 699999 SUBENT 10994007 900404 10994 7 1 BIB 5 11 10994 7 2 REACTION ((92-U-238(N,F)ELEM/MASS,IND,FY)/ 10994 7 3 (92-U-238(N,F)MASS,CHN,FY)) 10994 7 4 RESULT (FRIND) 10994 7 5 ERR-ANALYS (DATA-ERR) 1-SIGMA ERRORS INCLUDE UNCERTAINTIES IN: 10994 7 6 - GAMMA-RAY MEASUREMENTS 10994 7 7 - PHOTON ABUNDANCES 10994 7 8 - DETECTOR EFFICIENCY CALIBRATION (ESTIMATED 2%) 10994 7 9 - GAMMA SUMMING CORRECTIONS 10994 7 10 - TOTAL CHAIN YIELDS (5%) 10994 7 11 STATUS (DEP,10994003) 10994 7 12 HISTORY (900404A) UPDATE. 10994 7 13 ENDBIB 11 10994 7 14 COMMON 1 3 10994 7 15 ELEMENT 10994 7 16 NO-DIM 10994 7 17 61. 10994 7 18 ENDCOMMON 1 3 10994 7 19 DATA 5 3 10994 7 20 MASS ISOMER DATA DATA-ERR DATA-MAX 10994 7 21 NO-DIM NO-DIM NO-DIM NO-DIM NO-DIM 10994 7 22 148. 1. 1.6 -07 10994 7 23 148. 0. 1.3 -07 10994 7 24 150. 2.3 -05 0.7 -05 10994 7 25 ENDDATA 5 10994 7 26 ENDSUBENT 5 10994 799999 ENDENTRY 7 1099499999999 ENTRY 12813 891106 12813 0 1 SUBENT 12813001 891106 12813 1 1 BIB 13 25 12813 1 2 INSTITUTE (1USAWAS) 12813 1 3 REFERENCE (J,PR/C,30,1966,8412) 12813 1 4 (T,SEMKOW,8308) 12813 1 5 AUTHOR (T.M.SEMKOW,A.C.WAHL,L.ROBINSON) 12813 1 6 TITLE YIELDS OF IN AND SN PRODUCTS FROM THERMAL AND 12813 1 7 14-MEV NEUTRON INDUCED FISSION OF 235-U. 12813 1 8 FACILITY (CYCLO) 12813 1 9 KAMAN NUCLEAR MODEL A-711 SEALED TUBE TYPE NEUTRON 12813 1 10 GENERATOR. 12813 1 11 SAMPLE U-238 IMPURITY = 6.8 PERCENT. 12813 1 12 METHOD (RCHEM) SOLVENT EXTRACTION PROCEDURE 12813 1 13 DETECTOR (PROPC) METHANE GAS FLOW PRPORTIONAL COUNTERS. 12813 1 14 ANALYSIS FISSION YIELD RESULTS WERE OBTAINED FROM A LEAST- 12813 1 15 SQUARES ANALYSIS OF THE EXPERIMENTAL DATA. 12813 1 16 MONITOR ((92-U-235(N,F)56-BA-139,CUM,FY)/ 12813 1 17 (92-U-235(N,F)47-AG-111,CUM,FY)) 12813 1 18 ERR-ANALYS (DATA-ERR) THE UNCERTAINTIES INCLUDE LEAST-SQUARES 12813 1 19 ERRORS WHICH INCLUDE THE ERRORS OF YIELDS 12813 1 20 TAKEN FROM LITERATURE. 12813 1 21 UNCETAINTIES WERE PROPAGATED ACCORDING TO 12813 1 22 STATISTICAL METHODS WITH UTILIZATION OF 12813 1 23 CORRELATION ERRORS. 12813 1 24 STATUS (APRVD) A.C.WAHL, 85/8/30. 12813 1 25 HISTORY (850729C) 12813 1 26 (891106A) BIB UPDATE. 12813 1 27 ENDBIB 25 12813 1 28 COMMON 2 3 12813 1 29 MONIT MONIT-ERR 12813 1 30 NO-DIM NO-DIM 12813 1 31 4.24 0.52 12813 1 32 ENDCOMMON 2 3 12813 1 33 ENDSUBENT 2 12813 199999 SUBENT 12813006 850729 12813 6 1 BIB 4 11 12813 6 2 REACTION (92-U-235(N,F)ELEM/MASS,IND,FY) 12813 6 3 INC-SOURCE (D-T) 12813 6 4 DECAY-DATA ((1.)48-CD-121-G,12.5SEC) 12813 6 5 ((1.)48-CD-121-M,8.3SEC) 12813 6 6 ((2.)49-IN-121-G,23.1SEC) 12813 6 7 ((2.)49-IN-121-M,3.88MIN) 12813 6 8 ((3.)50-SN-121-G,27.0HR) 12813 6 9 ((3.)50-SN-121-M,55.YR) 12813 6 10 ((4.)50-SN-123-G,129.3D) 12813 6 11 ((4.)50-SN-123-M,40.1MIN) 12813 6 12 STATUS DATA TAKEN FROM THESIS TABLE 2. 12813 6 13 ENDBIB 11 12813 6 14 COMMON 1 3 12813 6 15 EN 12813 6 16 MEV 12813 6 17 14.3 12813 6 18 ENDCOMMON 1 3 12813 6 19 DATA 5 4 12813 6 20 ELEMENT MASS DATA DATA-ERR DECAY-FLAG 12813 6 21 NO-DIM NO-DIM PER-CENT PER-CENT NO-DIM 12813 6 22 48. 121. 0.499 0.235 1. 12813 6 23 49. 121. 0.455 0.115 2. 12813 6 24 50. 121. 0.049 0.057 3. 12813 6 25 50. 123. 0.13 0.13 4. 12813 6 26 ENDDATA 6 12813 6 27 ENDSUBENT 5 12813 699999 SUBENT 12813007 880906 12813 7 1 BIB 5 7 12813 7 2 REACTION (92-U-235(N,F)ELEM/MASS,CUM,FY) 12813 7 3 INC-SOURCE (D-T) 12813 7 4 DECAY-DATA ((1.)47-AG-121,0.72SEC) 12813 7 5 ((2.)49-IN-123-G,5.98SEC) 12813 7 6 ((2.)49-IN-123-M,47.8SEC) 12813 7 7 STATUS DATA TAKEN FROM THESIS TABLE 2. 12813 7 8 HISTORY (880906A) DATA UNITS CORRECTED. 12813 7 9 ENDBIB 7 12813 7 10 COMMON 1 3 12813 7 11 EN 12813 7 12 MEV 12813 7 13 14.3 12813 7 14 ENDCOMMON 1 3 12813 7 15 DATA 5 2 12813 7 16 ELEMENT MASS DATA DATA-ERR DECAY-FLAG 12813 7 17 NO-DIM NO-DIM PC/FIS PC/FIS NO-DIM 12813 7 18 47. 121. 0.152 0.185 1. 12813 7 19 49. 123. 1.13 0.24 2. 12813 7 20 ENDDATA 4 12813 7 21 ENDSUBENT 5 12813 799999 SUBENT 12813008 891106 12813 8 1 BIB 5 13 12813 8 2 REACTION ((92-U-235(N,F)ELEM/MASS,IND,FY)/ 12813 8 3 (92-U-235(N,F)MASS,CHN,FY)) 12813 8 4 RESULT (FRIND) 12813 8 5 INC-SOURCE (D-T) REACTION FOR 14 MEV NEUTRONS 12813 8 6 DECAY-DATA ((1.)48-CD-121-G,12.5SEC,B) 12813 8 7 ((1.)48-CD-121-M,8.3SEC,B) 12813 8 8 ((2.)49-IN-121-G,23.1SEC,B) 12813 8 9 ((2.)49-IN-121-M,3.88MIN,B) 12813 8 10 ((3.)50-SN-121-G,27.0HR) 12813 8 11 ((3.)50-SN-121-M,55.YR) 12813 8 12 ((4.)50-SN-123-G,129.3D) 12813 8 13 ((4.)50-SN-123-M,40.1MIN) 12813 8 14 STATUS DATA TAKEN FROM THESIS TABLE 3. 12813 8 15 ENDBIB 13 12813 8 16 COMMON 1 3 12813 8 17 EN 12813 8 18 MEV 12813 8 19 14.3 12813 8 20 ENDCOMMON 1 3 12813 8 21 DATA 5 4 12813 8 22 ELEMENT MASS DATA DATA-ERR DECAY-FLAG 12813 8 23 NO-DIM NO-DIM NO-DIM NO-DIM NO-DIM 12813 8 24 48. 121. 0.432 0.203 1. 12813 8 25 49. 121. 0.394 0.100 2. 12813 8 26 50. 121. 0.042 0.049 3. 12813 8 27 50. 123. 0.107 0.105 4. 12813 8 28 ENDDATA 6 12813 8 29 ENDSUBENT 5 12813 899999 SUBENT 12813009 891106 12813 9 1 BIB 5 8 12813 9 2 REACTION ((92-U-235(N,F)ELEM/MASS,CUM,FY)/ 12813 9 3 (92-U-235(N,F)MASS,CHN,FY)) 12813 9 4 RESULT (FRCUM) 12813 9 5 INC-SOURCE (D-T) 12813 9 6 DECAY-DATA ((1.)47-AG-121,0.72SEC) 12813 9 7 ((2.)49-IN-123-G,5.98SEC) 12813 9 8 ((2.)49-IN-123-M,47.8SEC) 12813 9 9 STATUS DATA TAKEN FROM THESIS TABLE 3. 12813 9 10 ENDBIB 8 12813 9 11 COMMON 1 3 12813 9 12 EN 12813 9 13 MEV 12813 9 14 14.3 12813 9 15 ENDCOMMON 1 3 12813 9 16 DATA 5 2 12813 9 17 ELEMENT MASS DATA DATA-ERR DECAY-FLAG 12813 9 18 NO-DIM NO-DIM NO-DIM NO-DIM NO-DIM 12813 9 19 47. 121. 0.132 0.160 1. 12813 9 20 49. 123. 0.893 0.190 2. 12813 9 21 ENDDATA 4 12813 9 22 ENDSUBENT 5 12813 999999 ENDENTRY 5 1281399999999 ENTRY 12895 891106 12895 0 1 SUBENT 12895001 891106 12895 1 1 BIB 11 39 12895 1 2 INSTITUTE (1USALAS) 12895 1 3 REFERENCE (J,PR/C,30,195,8407) 12895 1 4 AUTHOR (G.P.FORD,K.WOLFSBERG,B.R.ERDAL) 12895 1 5 TITLE INDEPENDENT YIELDS OF THE ISOMERS OF 133-XE AND 135-XE 12895 1 6 FOR NEUTRON INDUCED FISSION OF 233-U,235-U,238-U, 12895 1 7 239-PU, AND 242-AM-M. 12895 1 8 METHOD (RCHEM) TIMED CHEMICAL SEPARATION BY EMANATION METHOD 12895 1 9 DETECTOR (SOLST) SOLID STATE DETECTOR 12895 1 10 ANALYSIS DEMING'S(STATISTICAL ADJUSTMENT OF DATA,WILEY,1938) 12895 1 11 GENERALIZED LEAST-SQUARES METHOD WAS USED FOR 12895 1 12 OBTAINING INDEPENDENT YIELDS,ISOMER RATIOS AND 12895 1 13 THEIR ERRORS. 12895 1 14 DECAY-DATA ((1.)51-SB-133,2.5MIN) 12895 1 15 BRANCHING RATIO 133-SB TO 133-TE(M) = 0.165 12895 1 16 133-SB TO 133-TE(G) = 0.835 12895 1 17 ((1.)52-TE-133-M,55.4MIN) 12895 1 18 BRANCHING RATIO 133-TE(M) TO 133-TE(G) = 0.17 12895 1 19 133-TE(M) TO 133-I = 0.83 12895 1 20 ((1.)52-TE-133-G,12.45MIN) 12895 1 21 BRANCHING RATIO 133-TE(G) TO 133-I = 1.0 12895 1 22 ((1.)53-I-133-G,20.60HR) 12895 1 23 BRANCHING RATIO 133-I TO 133-XE(M) = 0.029 12895 1 24 133-I TO 133-XE(G) = 0.971 12895 1 25 ((1.)54-XE-133-M,2.19D,DG,233.,1.0) 12895 1 26 ((1.)54-XE-133-G,5.25D,DG,80.) 12895 1 27 ((2.)52-TE-135,17.5SEC) 12895 1 28 BRANCHING RATIO 135-TE TO 135-I = 1.0 12895 1 29 ((2.)53-I-135,6.64HR) 12895 1 30 BRANCHING RATIO 135-I TO 135-XE(M) = 0.147 12895 1 31 135-I TO 135-XE(G) = 0.853 12895 1 32 ((2.)54-XE-135-M,15.48MIN,DG,527.,1.0) 12895 1 33 ((2.)54-XE-135-G,9.104HR,DG,250.) 12895 1 34 ERR-ANALYS (DATA-ERR)THE QUOTED UNCERTAINTIES WERE OBTAINED FROM 12895 1 35 THE PROPAGATION OF ERRORS THROUGH THE LEAST-SQUARES 12895 1 36 ANALYSIS. 12895 1 37 STATUS (APRVD) G.P.FORD, 84/9/25. 12895 1 38 HISTORY (840823C) 12895 1 39 (851107A) BIB, DECAY DATA CORRECTIONS. 12895 1 40 (891106A) BIB UPDATE. 12895 1 41 ENDBIB 39 12895 1 42 NOCOMMON 0 0 12895 1 43 ENDSUBENT 0 12895 199999 SUBENT 12895005 891106 12895 5 1 BIB 5 16 12895 5 2 REACTION ((92-U-235(N,F)ELEM/MASS,IND,FY)/ 12895 5 3 (92-U-235(N,F)MASS,CHN,FY)) 12895 5 4 RESULT (FRIND) 12895 5 5 FACILITY (CCW,1USALAS)LOS ALAMOS COCKROFT-WALTON ACCELERATOR 12895 5 6 (ICTR,1USALRL) LAWRENCE LIVERMORE INSULATED CORE 12895 5 7 TRANSFORMER FACILITY 12895 5 8 INC-SOURCE COCKROFT-WALTON- FLUX= 7*10**8 N/CM**2/SEC 12895 5 9 LAWRENCE LIVERMORE NATIONAL LAB ICT FACILITY 12895 5 10 FLUX =2*10**11 N/CM**2/SEC 12895 5 11 SAMPLE ISOTOPIC COMPOSITION OF THE SAMPLES - 12895 5 12 (PERCENT) 12895 5 13 U-233 0.02 12895 5 14 U-234 1.12 0.065 1.07 1.10 12895 5 15 U-235 94.13 99.727 93.13 93.09 12895 5 16 U-236 0.080 0.71 0.16 12895 5 17 U-238 4.75 0.128 5.01 5.63 12895 5 18 ENDBIB 16 12895 5 19 COMMON 2 3 12895 5 20 EN ELEMENT 12895 5 21 MEV NO-DIM 12895 5 22 14.8 54. 12895 5 23 ENDCOMMON 2 3 12895 5 24 DATA 5 6 12895 5 25 MASS ISOMER DATA DATA-ERR DECAY-FLAG 12895 5 26 NO-DIM NO-DIM NO-DIM NO-DIM NO-DIM 12895 5 27 133. 1. 0.0259 0.0012 1. 12895 5 28 133. 0. 0.00510 0.00055 1. 12895 5 29 133. 0.0310 0.0014 1. 12895 5 30 135. 1. 0.1599 0.0070 2. 12895 5 31 135. 0. 0.083 0.011 2. 12895 5 32 135. 0.2431 0.0075 2. 12895 5 33 ENDDATA 8 12895 5 34 ENDSUBENT 5 12895 599999 SUBENT 12895007 891106 12895 7 1 BIB 5 13 12895 7 2 REACTION ((92-U-238(N,F)ELEM/MASS,IND,FY)/ 12895 7 3 (92-U-238(N,F)MASS,CHN,FY)) 12895 7 4 RESULT (FRIND) 12895 7 5 FACILITY (CCW,1USALAS)LOS ALAMOS COCKROFT-WALTON ACCELERATOR 12895 7 6 (ICTR,1USALRL) LAWRENCE LIVERMORE INSULATED CORE 12895 7 7 TRANSFORMER FACILITY 12895 7 8 INC-SOURCE COCKROFT-WALTON- FLUX= 7*10**8 N/CM**2/SEC 12895 7 9 LAWRENCE LIVERMORE NATIONAL LAB ICT FACILITY 12895 7 10 FLUX =2*10**11 N/CM**2/SEC 12895 7 11 SAMPLE ISOTOPIC COMPOSITION OF THE SAMPLE - 12895 7 12 (PERCENT) 12895 7 13 U-235 0.0006 12895 7 14 U-238 99.999 12895 7 15 ENDBIB 13 12895 7 16 COMMON 2 3 12895 7 17 EN ELEMENT 12895 7 18 MEV NO-DIM 12895 7 19 14.8 54. 12895 7 20 ENDCOMMON 2 3 12895 7 21 DATA 5 6 12895 7 22 MASS ISOMER DATA DATA-ERR DECAY-FLAG 12895 7 23 NO-DIM NO-DIM NO-DIM NO-DIM NO-DIM 12895 7 24 133. 1. 0.00238 0.00010 1. 12895 7 25 133. 0. 0.00047 0.00014 1. 12895 7 26 133. 0.00286 0.00014 1. 12895 7 27 135. 1. 0.0287 0.0041 2. 12895 7 28 135. 0. 0.0188 0.0023 2. 12895 7 29 135. 0.0497 0.0032 2. 12895 7 30 ENDDATA 8 12895 7 31 ENDSUBENT 5 12895 799999 SUBENT 12895010 891106 12895 10 1 BIB 5 16 12895 10 2 REACTION ((94-PU-239(N,F)ELEM/MASS,IND,FY)/ 12895 10 3 (94-PU-239(N,F)MASS,CHN,FY)) 12895 10 4 RESULT (FRIND) 12895 10 5 FACILITY (CCW,1USALAS)LOS ALAMOS COCKROFT-WALTON ACCELERATOR 12895 10 6 (ICTR,1USALRL) LAWRENCE LIVERMORE INSULATED CORE 12895 10 7 TRANSFORMER FACILITY 12895 10 8 INC-SOURCE COCKROFT-WALTON- FLUX= 7*10**8 N/CM**2/SEC 12895 10 9 LAWRENCE LIVERMORE NATIONAL LAB ICT FACILITY 12895 10 10 FLUX =2*10**11 N/CM**2/SEC 12895 10 11 SAMPLE ISOTOPIC COMPOSITION OF THE SAMPLES - 12895 10 12 (PERCENT) 12895 10 13 PU-238 0.002 12895 10 14 PU-239 94.41 99.27 12895 10 15 PU-240 5.23 0.71 12895 10 16 PU-241 0.36 0.01 12895 10 17 PU-242 0.001(MAXIMUM) 12895 10 18 ENDBIB 16 12895 10 19 COMMON 2 3 12895 10 20 EN ELEMENT 12895 10 21 MEV NO-DIM 12895 10 22 14.8 54. 12895 10 23 ENDCOMMON 2 3 12895 10 24 DATA 5 6 12895 10 25 MASS ISOMER DATA DATA-ERR DECAY-FLAG 12895 10 26 NO-DIM NO-DIM NO-DIM NO-DIM NO-DIM 12895 10 27 133. 1. 0.0575 0.0081 1. 12895 10 28 133. 0. 0.0170 0.0021 1. 12895 10 29 133. 0.0751 0.0085 1. 12895 10 30 135. 1. 0.317 0.021 2. 12895 10 31 135. 0. 0.117 0.025 2. 12895 10 32 135. 0.4337 0.0097 2. 12895 10 33 ENDDATA 8 12895 10 34 ENDSUBENT 5 12895 1099999 ENDENTRY 4 1289599999999 ENTRY 13059 890518 13059 0 1 SUBENT 13059001 890518 13059 1 1 BIB 9 12 13059 1 2 INSTITUTE (1USALRL) 13059 1 3 REFERENCE (J,PR,124,544,61) 13059 1 4 AUTHOR (H.B.LEVY,H.G.HICKS,W.E.NERVIK,P.C.STEVENSON, 13059 1 5 J.B.NIDAY,J.C.ARMSTRONG JR) 13059 1 6 TITLE RADIOCHEMICAL STUDIES OF NEUTRON FISSION OF U235 AND 13059 1 7 U238 AND THE TWO-MODE FISSION HYPOTHESIS 13059 1 8 FACILITY (CYCLO) 13059 1 9 METHOD (RCHEM) 13059 1 10 ERR-ANALYS DATA UNCERTAINTIES ARE AVERAGE OVERALL STANDARD 13059 1 11 DEVIATIONS, AND INCLUDE ONLY RANDOM ERRORS. 13059 1 12 STATUS (RIDER) REFERENCE 61LEV1 13059 1 13 HISTORY (890510C) VM 13059 1 14 ENDBIB 12 13059 1 15 NOCOMMON 0 0 13059 1 16 ENDSUBENT 0 13059 199999 SUBENT 13059003 890518 13059 3 1 BIB 6 10 13059 3 2 REACTION (((92-U-235(N,F)ELEM/MASS,CUM,FY,,SPA)/ 13059 3 3 (92-U-235(N,F)42-MO-99,CUM,FY,,SPA))// 13059 3 4 ((92-U-235(N,F)ELEM/MASS,CUM,FY,,MXW)/ 13059 3 5 (92-U-235(N,F)42-MO-99,CUM,FY,,MXW))) 13059 3 6 RESULT (RVAL) 13059 3 7 INC-SOURCE NEUTRONS WERE OBTAINED BY BOMBARDMENT OF COPPER 13059 3 8 WITH 24 MEV DEUTERONS 13059 3 9 SAMPLE NATURAL URANIUM 13059 3 10 ANALYSIS AVERAGE OF 2 MEASUREMENTS 13059 3 11 CORRECTION CORRECTED FOR PRESENCE OF 238U 13059 3 12 ENDBIB 10 13059 3 13 COMMON 3 3 13059 3 14 EN-DUM-NM EN-DUM-DN DATA-ERR 13059 3 15 MEV EV PER-CENT 13059 3 16 14. 0.0253 5. 13059 3 17 ENDCOMMON 3 3 13059 3 18 DATA 3 12 13059 3 19 ELEMENT MASS DATA 13059 3 20 NO-DIM NO-DIM NO-DIM 13059 3 21 38. 89. 0.81 13059 3 22 46. 109. 14.9 13059 3 23 46. 112. 23.4 13059 3 24 47. 111. 15.5 13059 3 25 48. 115. 20.5 13059 3 26 55. 136. 9.99 13059 3 27 55. 137. 0.98 13059 3 28 56. 140. 0.945 13059 3 29 60. 147. 0.88 13059 3 30 62. 153. 1.37 13059 3 31 63. 156. 2.43 13059 3 32 65. 161. 18.2 13059 3 33 ENDDATA 14 13059 3 34 ENDSUBENT 3 13059 399999 SUBENT 13059004 890518 13059 4 1 BIB 5 9 13059 4 2 REACTION (((92-U-235(N,F)ELEM/MASS,CUM,FY,,SPA)/ 13059 4 3 (92-U-235(N,F)42-MO-99,CUM,FY,,SPA))// 13059 4 4 ((92-U-235(N,F)ELEM/MASS,CUM,FY,,MXW)/ 13059 4 5 (92-U-235(N,F)42-MO-99,CUM,FY,,MXW))) 13059 4 6 RESULT (RVAL) 13059 4 7 INC-SOURCE NEUTRONS WERE OBTAINED BY BOMBARDMENT OF ALUMINUM 13059 4 8 WITH 48 MEV ALPHAS 13059 4 9 ANALYSIS AVERAGE OF 2 MEASUREMENTS 13059 4 10 CORRECTION CORRECTED FOR PRESENCE OF 238U 13059 4 11 ENDBIB 9 13059 4 12 COMMON 3 3 13059 4 13 EN-DUM-NM EN-DUM-DN DATA-ERR 13059 4 14 MEV EV PER-CENT 13059 4 15 14. 0.0253 5. 13059 4 16 ENDCOMMON 3 3 13059 4 17 DATA 3 13 13059 4 18 ELEMENT MASS DATA 13059 4 19 NO-DIM NO-DIM NO-DIM 13059 4 20 38. 89. 0.825 13059 4 21 39. 91. 1.01 13059 4 22 46. 109. 14.05 13059 4 23 46. 112. 25.4 13059 4 24 47. 111. 18.5 13059 4 25 48. 115. 22.9 13059 4 26 55. 136. 13.75 13059 4 27 55. 137. 1.03 13059 4 28 56. 140. 0.915 13059 4 29 60. 147. 0.925 13059 4 30 62. 153. 1.445 13059 4 31 63. 156. 2.72 13059 4 32 65. 161. 23.85 13059 4 33 ENDDATA 15 13059 4 34 ENDSUBENT 3 13059 499999 SUBENT 13059005 890518 13059 5 1 BIB 4 7 13059 5 2 REACTION (((92-U-235(N,F)ELEM/MASS,CUM,FY,,SPA)/ 13059 5 3 (92-U-235(N,F)42-MO-99,CUM,FY,,SPA))// 13059 5 4 ((92-U-235(N,F)ELEM/MASS,CUM,FY,,MXW)/ 13059 5 5 (92-U-235(N,F)42-MO-99,CUM,FY,,MXW))) 13059 5 6 RESULT (RVAL) 13059 5 7 INC-SOURCE (A-BE) BOMBARDMENT OF BERYLLIUM WITH 48 MEV ALPHAS 13059 5 8 CORRECTION CORRECTED FOR PRESENCE OF 238U 13059 5 9 ENDBIB 7 13059 5 10 COMMON 3 3 13059 5 11 EN-DUM-NM EN-DUM-DN DATA-ERR 13059 5 12 MEV EV PER-CENT 13059 5 13 14. 0.0253 5. 13059 5 14 ENDCOMMON 3 3 13059 5 15 DATA 5 10 13059 5 16 ELEMENT MASS DATA DATA-ERR DATA-ERR 13059 5 17 NO-DIM NO-DIM NO-DIM PER-CENT NO-DIM 13059 5 18 38. 89. 0.83 5. 13059 5 19 39. 91. 1.02 5. 13059 5 20 47. 111. 26.1 1.6 13059 5 21 48. 115. 32.2 5. 13059 5 22 55. 136. 18.6 5. 13059 5 23 55. 137. 1.06 5. 13059 5 24 56. 140. 0.93 5. 13059 5 25 62. 153. 1.46 5. 13059 5 26 63. 156. 2.99 5. 13059 5 27 65. 161. 30.8 5. 13059 5 28 ENDDATA 12 13059 5 29 ENDSUBENT 5 13059 599999 SUBENT 13059006 890518 13059 6 1 BIB 4 7 13059 6 2 REACTION (((92-U-235(N,F)ELEM/MASS,CUM,FY,,SPA)/ 13059 6 3 (92-U-235(N,F)42-MO-99,CUM,FY,,SPA))// 13059 6 4 ((92-U-235(N,F)ELEM/MASS,CUM,FY,,MXW)/ 13059 6 5 (92-U-235(N,F)42-MO-99,CUM,FY,,MXW))) 13059 6 6 RESULT (RVAL) 13059 6 7 INC-SOURCE (D-BE) BOMBARDMENT OF BERYLLIUM WITH 24 MEV DEUTERONS 13059 6 8 CORRECTION CORRECTED FOR PRESENCE OF 238U 13059 6 9 ENDBIB 7 13059 6 10 COMMON 3 3 13059 6 11 EN-DUM-NM EN-DUM-DN DATA-ERR 13059 6 12 MEV EV PER-CENT 13059 6 13 14. 0.0253 5. 13059 6 14 ENDCOMMON 3 3 13059 6 15 DATA 3 13 13059 6 16 ELEMENT MASS DATA 13059 6 17 NO-DIM NO-DIM NO-DIM 13059 6 18 38. 89. 0.84 13059 6 19 39. 91. 1.06 13059 6 20 46. 109. 21.4 13059 6 21 46. 112. 34.1 13059 6 22 47. 111. 26.5 13059 6 23 48. 115. 33.6 13059 6 24 55. 136. 18.5 13059 6 25 55. 137. 1.01 13059 6 26 56. 140. 0.86 13059 6 27 60. 147. 0.88 13059 6 28 62. 153. 1.48 13059 6 29 63. 156. 3.00 13059 6 30 65. 161. 32.1 13059 6 31 ENDDATA 15 13059 6 32 ENDSUBENT 3 13059 699999 SUBENT 13059007 890518 13059 7 1 BIB 5 8 13059 7 2 REACTION (((92-U-235(N,F)ELEM/MASS,CUM,FY,,SPA)/ 13059 7 3 (92-U-235(N,F)42-MO-99,CUM,FY,,SPA))// 13059 7 4 ((92-U-235(N,F)ELEM/MASS,CUM,FY,,MXW)/ 13059 7 5 (92-U-235(N,F)42-MO-99,CUM,FY,,MXW))) 13059 7 6 RESULT (RVAL) 13059 7 7 INC-SOURCE (D-LI) BOMBARDMENT OF LITHIUM WITH 24 MEV DEUTERONS 13059 7 8 ANALYSIS AVERAGE OF 3 MEASUREMENTS 13059 7 9 CORRECTION CORRECTED FOR PRESENCE OF 238U 13059 7 10 ENDBIB 8 13059 7 11 COMMON 3 3 13059 7 12 EN-DUM-NM EN-DUM-DN DATA-ERR 13059 7 13 MEV EV PER-CENT 13059 7 14 14. 0.0253 5. 13059 7 15 ENDCOMMON 3 3 13059 7 16 DATA 3 13 13059 7 17 ELEMENT MASS DATA 13059 7 18 NO-DIM NO-DIM NO-DIM 13059 7 19 38. 89. 0.89 13059 7 20 39. 91. 1.09 13059 7 21 46. 109. 25.3 13059 7 22 46. 112. 44.6 13059 7 23 47. 111. 34.2 13059 7 24 48. 115. 42.5 13059 7 25 55. 136. 23.7 13059 7 26 55. 137. 1.11 13059 7 27 56. 140. 0.99 13059 7 28 60. 147. 0.99 13059 7 29 62. 153. 1.67 13059 7 30 63. 156. 3.55 13059 7 31 65. 161. 41.4 13059 7 32 ENDDATA 15 13059 7 33 ENDSUBENT 3 13059 799999 SUBENT 13059009 890518 13059 9 1 BIB 5 9 13059 9 2 REACTION (((92-U-238(N,F)ELEM/MASS,CUM,FY,,SPA)/ 13059 9 3 (92-U-238(N,F)42-MO-99,CUM,FY,,SPA))// 13059 9 4 ((92-U-235(N,F)ELEM/MASS,CUM,FY,,MXW)/ 13059 9 5 (92-U-235(N,F)42-MO-99,CUM,FY,,MXW))) 13059 9 6 RESULT (RVAL) 13059 9 7 INC-SOURCE NEUTRONS WERE OBTAINED BY BOMBARDMENT OF COPPER 13059 9 8 WITH 24 MEV DEUTERONS 13059 9 9 ANALYSIS AVERAGE OF 2 MEASUREMENTS 13059 9 10 CORRECTION CORRECTED FOR PRESENCE OF 235U 13059 9 11 ENDBIB 9 13059 9 12 COMMON 2 3 13059 9 13 EN-DUM-NM EN-DUM-DN 13059 9 14 MEV EV 13059 9 15 14. 0.0253 13059 9 16 ENDCOMMON 2 3 13059 9 17 DATA 5 13 13059 9 18 ELEMENT MASS DATA DATA-ERR DATA-ERR 13059 9 19 NO-DIM NO-DIM NO-DIM PER-CENT NO-DIM 13059 9 20 38. 89. 0.52 5. 13059 9 21 39. 91. 0.76 5. 13059 9 22 46. 109. 21.4 5. 13059 9 23 46. 112. 26.0 5. 13059 9 24 47. 111. 18.8 13059 9 25 48. 115. 21.9 5. 13059 9 26 55. 136. 1.40 0.10 13059 9 27 55. 137. 0.94 5. 13059 9 28 56. 140. 0.90 5. 13059 9 29 60. 147. 1.02 5. 13059 9 30 62. 153. 2.64 5. 13059 9 31 63. 156. 6.37 5. 13059 9 32 65. 161. 48.3 5. 13059 9 33 ENDDATA 15 13059 9 34 ENDSUBENT 5 13059 999999 SUBENT 13059010 890518 13059 10 1 BIB 5 9 13059 10 2 REACTION (((92-U-238(N,F)ELEM/MASS,CUM,FY,,SPA)/ 13059 10 3 (92-U-238(N,F)42-MO-99,CUM,FY,,SPA))// 13059 10 4 ((92-U-235(N,F)ELEM/MASS,CUM,FY,,MXW)/ 13059 10 5 (92-U-235(N,F)42-MO-99,CUM,FY,,MXW))) 13059 10 6 RESULT (RVAL) 13059 10 7 INC-SOURCE NEUTRONS WERE OBTAINED BY BOMBARDMENT OF ALUMINUM 13059 10 8 WITH 48 MEV ALPHAS 13059 10 9 ANALYSIS AVERAGE OF 2 MEASUREMENTS 13059 10 10 CORRECTION CORRECTED FOR PRESENCE OF 235U 13059 10 11 ENDBIB 9 13059 10 12 COMMON 3 3 13059 10 13 EN-DUM-NM EN-DUM-DN DATA-ERR 13059 10 14 MEV EV PER-CENT 13059 10 15 14. 0.0253 5. 13059 10 16 ENDCOMMON 3 3 13059 10 17 DATA 3 13 13059 10 18 ELEMENT MASS DATA 13059 10 19 NO-DIM NO-DIM NO-DIM 13059 10 20 38. 89. 0.54 13059 10 21 39. 91. 0.77 13059 10 22 46. 109. 21.25 13059 10 23 46. 112. 28.85 13059 10 24 47. 111. 21.1 13059 10 25 48. 115. 23.8 13059 10 26 55. 136. 2.02 13059 10 27 55. 137. 0.98 13059 10 28 56. 140. 0.91 13059 10 29 60. 147. 1.12 13059 10 30 62. 153. 2.805 13059 10 31 63. 156. 6.66 13059 10 32 65. 161. 53.65 13059 10 33 ENDDATA 15 13059 10 34 ENDSUBENT 3 13059 1099999 SUBENT 13059011 890518 13059 11 1 BIB 4 7 13059 11 2 REACTION (((92-U-238(N,F)ELEM/MASS,CUM,FY,,SPA)/ 13059 11 3 (92-U-238(N,F)42-MO-99,CUM,FY,,SPA))// 13059 11 4 ((92-U-235(N,F)ELEM/MASS,CUM,FY,,MXW)/ 13059 11 5 (92-U-235(N,F)42-MO-99,CUM,FY,,MXW))) 13059 11 6 RESULT (RVAL) 13059 11 7 INC-SOURCE (A-BE) BOMBARDMENT OF BERYLLIUM WITH 48 MEV ALPHAS 13059 11 8 CORRECTION CORRECTED FOR PRESENCE OF 235U 13059 11 9 ENDBIB 7 13059 11 10 COMMON 2 3 13059 11 11 EN-DUM-NM EN-DUM-DN 13059 11 12 MEV EV 13059 11 13 14. 0.0253 13059 11 14 ENDCOMMON 2 3 13059 11 15 DATA 5 11 13059 11 16 ELEMENT MASS DATA DATA-ERR DATA-ERR 13059 11 17 NO-DIM NO-DIM NO-DIM PER-CENT NO-DIM 13059 11 18 38. 89. 0.54 5. 13059 11 19 39. 91. 0.74 5. 13059 11 20 47. 111. 30.0 1.8 13059 11 21 48. 115. 32.5 5. 13059 11 22 55. 136. 3.07 0.21 13059 11 23 55. 137. 0.92 5. 13059 11 24 56. 140. 0.87 5. 13059 11 25 60. 147. 0.95 5. 13059 11 26 62. 153. 2.70 5. 13059 11 27 63. 156. 6.52 0.39 13059 11 28 65. 161. 64.2 5. 13059 11 29 ENDDATA 13 13059 11 30 ENDSUBENT 5 13059 1199999 SUBENT 13059012 890518 13059 12 1 BIB 5 8 13059 12 2 REACTION (((92-U-238(N,F)ELEM/MASS,CUM,FY,,SPA)/ 13059 12 3 (92-U-238(N,F)42-MO-99,CUM,FY,,SPA))// 13059 12 4 ((92-U-235(N,F)ELEM/MASS,CUM,FY,,MXW)/ 13059 12 5 (92-U-235(N,F)42-MO-99,CUM,FY,,MXW))) 13059 12 6 RESULT (RVAL) 13059 12 7 INC-SOURCE (D-BE) BOMBARDMENT OF BERYLLIUM WITH 24 MEV DEUTERONS 13059 12 8 ANALYSIS AVERAGE OF 2 MEASUREMENTS 13059 12 9 CORRECTION CORRECTED FOR PRESENCE OF 235U 13059 12 10 ENDBIB 8 13059 12 11 COMMON 2 3 13059 12 12 EN-DUM-NM EN-DUM-DN 13059 12 13 MEV EV 13059 12 14 14. 0.0253 13059 12 15 ENDCOMMON 2 3 13059 12 16 DATA 5 12 13059 12 17 ELEMENT MASS DATA DATA-ERR DATA-ERR 13059 12 18 NO-DIM NO-DIM NO-DIM PER-CENT NO-DIM 13059 12 19 39. 91. 0.76 5. 13059 12 20 46. 109. 27.2 5. 13059 12 21 46. 112. 36.1 5. 13059 12 22 47. 111. 29.3 5. 13059 12 23 48. 115. 33.4 5. 13059 12 24 55. 136. 2.32 0.16 13059 12 25 55. 137. 0.91 5. 13059 12 26 56. 140. 0.83 5. 13059 12 27 60. 147. 1.04 5. 13059 12 28 62. 153. 2.85 5. 13059 12 29 63. 156. 7.14 5. 13059 12 30 65. 161. 68.0 13059 12 31 ENDDATA 14 13059 12 32 ENDSUBENT 5 13059 1299999 SUBENT 13059013 890518 13059 13 1 BIB 5 8 13059 13 2 REACTION (((92-U-238(N,F)ELEM/MASS,CUM,FY,,SPA)/ 13059 13 3 (92-U-238(N,F)42-MO-99,CUM,FY,,SPA))// 13059 13 4 ((92-U-235(N,F)ELEM/MASS,CUM,FY,,MXW)/ 13059 13 5 (92-U-235(N,F)42-MO-99,CUM,FY,,MXW))) 13059 13 6 RESULT (RVAL) 13059 13 7 INC-SOURCE (D-LI) BOMBARDMENT OF LITHIUM WITH 24 MEV DEUTERONS 13059 13 8 ANALYSIS AVERAGE OF 3 MEASUREMENTS 13059 13 9 CORRECTION CORRECTED FOR PRESENCE OF 235U 13059 13 10 ENDBIB 8 13059 13 11 COMMON 2 3 13059 13 12 EN-DUM-NM EN-DUM-DN 13059 13 13 MEV EV 13059 13 14 14. 0.0253 13059 13 15 ENDCOMMON 2 3 13059 13 16 DATA 4 13 13059 13 17 ELEMENT MASS DATA DATA-ERR 13059 13 18 NO-DIM NO-DIM NO-DIM NO-DIM 13059 13 19 38. 89. 0.565 5. 13059 13 20 39. 91. 0.74 13059 13 21 46. 109. 29.2 13059 13 22 46. 112. 41.6 13059 13 23 47. 111. 34.2 5. 13059 13 24 48. 115. 37.5 5. 13059 13 25 55. 136. 3.27 13059 13 26 55. 137. 0.94 5. 13059 13 27 56. 140. 0.90 5. 13059 13 28 60. 147. 1.10 5. 13059 13 29 62. 153. 2.87 13059 13 30 63. 156. 7.33 13059 13 31 65. 161. 76.9 13059 13 32 ENDDATA 15 13059 13 33 ENDSUBENT 4 13059 1399999 ENDENTRY 11 1305999999999 ENTRY 13061 890518 13061 0 1 SUBENT 13061001 890518 13061 1 1 BIB 11 12 13061 1 2 INSTITUTE (1USAARK) 13061 1 3 REFERENCE (J,PR,126,627,6204) 13061 1 4 AUTHOR (K.M.BROOM) 13061 1 5 TITLE 14.7 MEV NEUTRON-INDUCED FISSION OF U-238 13061 1 6 FACILITY (CCW) 13061 1 7 INC-SOURCE (D-T) 13061 1 8 SAMPLE URANIUM OXIDE 84.75% URANIUM 13061 1 9 ISOTOPIC COMPOSITION 99.989% 238U, 0.011% 235U 13061 1 10 METHOD (RCHEM) 13061 1 11 ERR-ANALYS DATA UNCERTAINTIES GIVEN ARE MOST PROBABLE ERRORS 13061 1 12 STATUS (RIDER) REFERENCE 62BRO1 13061 1 13 HISTORY (890511C) VM 13061 1 14 ENDBIB 12 13061 1 15 COMMON 2 3 13061 1 16 EN EN-RSL 13061 1 17 MEV MEV 13061 1 18 14.7 0.4 13061 1 19 ENDCOMMON 2 3 13061 1 20 ENDSUBENT 2 13061 199999 SUBENT 13061002 890518 13061 2 1 BIB 2 3 13061 2 2 REACTION (92-U-238(N,F)56-BA-140,CUM,FY) 13061 2 3 MONITOR ((MONIT1)13-AL-27(N,A)11-NA-24,,SIG) 13061 2 4 ((MONIT2)92-U-238(N,F),,SIG) 13061 2 5 ENDBIB 3 13061 2 6 NOCOMMON 0 0 13061 2 7 DATA 5 1 13061 2 8 DATA DATA-ERR MONIT1 MONIT2 MONIT2-ERR 13061 2 9 PC/FIS PC/FIS MB B B 13061 2 10 4.3 0.4 115. 1.13 0.05 13061 2 11 ENDDATA 3 13061 2 12 ENDSUBENT 5 13061 299999 SUBENT 13061003 890518 13061 3 1 BIB 2 2 13061 3 2 REACTION (92-U-238(N,F)ELEM/MASS,CUM,FY) 13061 3 3 MONITOR (92-U-238(N,F)56-BA-140,CUM,FY) 13061 3 4 ENDBIB 2 13061 3 5 COMMON 2 3 13061 3 6 MONIT MONIT-ERR 13061 3 7 PC/FIS PC/FIS 13061 3 8 4.3 0.4 13061 3 9 ENDCOMMON 2 3 13061 3 10 DATA 4 11 13061 3 11 ELEMENT MASS DATA DATA-ERR 13061 3 12 NO-DIM NO-DIM PC/FIS PC/FIS 13061 3 13 38. 89. 2.0 0.2 13061 3 14 38. 90. 3.4 0.3 13061 3 15 38. 91. 2.6 0.3 13061 3 16 47. 111. 0.6 0.1 13061 3 17 47. 113. 0.6 0.1 13061 3 18 53. 131. 2.7 0.2 13061 3 19 53. 132. 4.5 0.4 13061 3 20 53. 133. 2.6 0.3 13061 3 21 53. 134. 4.7 0.5 13061 3 22 53. 135. 5.0 0.5 13061 3 23 56. 139. 4.4 0.5 13061 3 24 ENDDATA 13 13061 3 25 ENDSUBENT 4 13061 399999 ENDENTRY 3 1306199999999 ENTRY 13075 890518 13075 0 1 SUBENT 13075001 890518 13075 1 1 BIB 12 17 13075 1 2 INSTITUTE (1USAARK) 13075 1 3 REFERENCE (J,JIN,27,503,65) 13075 1 4 AUTHOR (T.MO,P.K.KURODA) 13075 1 5 TITLE YIELDS OF ZIRCONIUM ISOTOPES FROM SPONTANEOUS AND 14.7 13075 1 6 MEV NEUTRON-INDUCED FISSION OF URANIUM-238 13075 1 7 FACILITY (CCW) 13075 1 8 INC-SOURCE (D-T) 13075 1 9 SAMPLE DEPLETED URANIUM TRIOXIDE. ISOTOPIC COMPOSITION: 13075 1 10 99.989% 238U, 0.011% 235U. 13075 1 11 NATURAL URANIUM IN URANYL NITRATE HEXAHYDRATE. ISOTOPIC13075 1 12 COMPOSITION ASSUMED TO BE 99.276% 238U, 0.719% 235U. 13075 1 13 METHOD (RCHEM) 13075 1 14 DETECTOR (PROPC) 2PI END-WINDOW METHANE-FLOW PROPORTIONAL 13075 1 15 COUNTER 13075 1 16 ERR-ANALYS NO INFORMATION 13075 1 17 STATUS (RIDER) REFERENCE 65MO 1 13075 1 18 HISTORY (890512C) VM 13075 1 19 ENDBIB 17 13075 1 20 NOCOMMON 0 0 13075 1 21 ENDSUBENT 0 13075 199999 SUBENT 13075002 890518 13075 2 1 BIB 2 3 13075 2 2 REACTION (92-U-238(N,F)42-MO-99,CUM,FY) 13075 2 3 MONITOR (13-AL-27(N,A)11-NA-24,,SIG) 13075 2 4 ((MONIT1)92-U-238(N,F),,SIG) 13075 2 5 ENDBIB 3 13075 2 6 COMMON 2 3 13075 2 7 EN EN-RSL 13075 2 8 MEV MEV 13075 2 9 14.7 0.4 13075 2 10 ENDCOMMON 2 3 13075 2 11 DATA 4 1 13075 2 12 DATA DATA-ERR MONIT1 MONIT1-ERR 13075 2 13 PC/FIS PC/FIS B B 13075 2 14 5.7 0.5 1.13 0.05 13075 2 15 ENDDATA 3 13075 2 16 ENDSUBENT 4 13075 299999 SUBENT 13075003 890518 13075 3 1 BIB 2 2 13075 3 2 REACTION (92-U-238(N,F)ELEM/MASS,CUM,FY) 13075 3 3 MONITOR (92-U-238(N,F)42-MO-99,CUM,FY) 13075 3 4 ENDBIB 2 13075 3 5 COMMON 4 3 13075 3 6 EN EN-RSL MONIT MONIT-ERR 13075 3 7 MEV MEV PC/FIS PC/FIS 13075 3 8 14.7 0.4 5.7 0.5 13075 3 9 ENDCOMMON 4 3 13075 3 10 DATA 4 2 13075 3 11 ELEMENT MASS DATA DATA-ERR 13075 3 12 NO-DIM NO-DIM PC/FIS PC/FIS 13075 3 13 40. 95. 6.1 0.6 13075 3 14 40. 97. 4.7 0.5 13075 3 15 ENDDATA 4 13075 3 16 ENDSUBENT 4 13075 399999 ENDENTRY 3 1307599999999 ENTRY 13077 890518 13077 0 1 SUBENT 13077001 890518 13077 1 1 BIB 12 17 13077 1 2 INSTITUTE (1USALAS) 13077 1 3 REFERENCE (J,PR/B,137,(4),826,6502) 13077 1 4 AUTHOR (G.P.FORD,R.B.LEACHMAN) 13077 1 5 TITLE FISSION MASS YIELD DEPENDENCE ON ANGULAR MOMENTUM 13077 1 6 FACILITY (VDG) FOR 4.7, 9.1, 16.3, 17.2 MEV NEUTRONS 13077 1 7 (CCW) FOR 13.3, 14.1, 14.9 MEV NEUTRONS 13077 1 8 (CYCLO) FOR 9.1 MEV NEUTRONS 13077 1 9 INC-SOURCE (D-D) FOR 4.1, 9.1 MEV NEUTRONS 13077 1 10 (D-T) FOR 13 TO 17 MEV NEUTRONS 13077 1 11 METHOD (RCHEM) 13077 1 12 MONITOR (6-C-12(N,N+2A)2-HE-4,,SIG) 13077 1 13 CORRECTION NOT CORRECTED FOR FISSIONS FROM MINORITY ISOTOPES 13077 1 14 ERR-ANALYS DATA UNCERTAINTIES GIVEN INCLUDE STATISTICAL 13077 1 15 UNCERTAINTY, DECAY UNCERTAINTIES, UNCERTAINTIES 13077 1 16 IN REPRODUCIBILITY OF CHEMICAL PROCEDURES. 13077 1 17 STATUS (RIDER) REFERENCE 65FOR2 13077 1 18 HISTORY (881017T) 13077 1 19 ENDBIB 17 13077 1 20 COMMON 1 3 13077 1 21 EN-NRM 13077 1 22 MEV 13077 1 23 16.3 13077 1 24 ENDCOMMON 1 3 13077 1 25 ENDSUBENT 1 13077 199999 SUBENT 13077002 890518 13077 2 1 BIB 2 3 13077 2 2 REACTION (92-U-235(N,F)ELEM/MASS,CUM,FY) 13077 2 3 SAMPLE ISOTOPIC COMPOSITION OF SAMPLE: 93.4% 235U, 1.1% 234U, 13077 2 4 5.5% 238U. 13077 2 5 ENDBIB 3 13077 2 6 NOCOMMON 0 0 13077 2 7 DATA 7 30 13077 2 8 EN EN-RSL ELEMENT MASS ISOMER DATA 13077 2 9 DATA-ERR 13077 2 10 MEV MEV NO-DIM NO-DIM NO-DIM PC/FIS 13077 2 11 PC/FIS 13077 2 12 13.4 0.17 46. 109. 1.09 13077 2 13 0.04 13077 2 14 13.4 0.17 46. 112. 0.96 13077 2 15 0.02 13077 2 16 13.4 0.17 47. 111. 0.992 13077 2 17 0.016 13077 2 18 13.4 0.17 47. 113. 0.720 13077 2 19 0.017 13077 2 20 14.1 0.16 46. 109. 1.22 13077 2 21 0.06 13077 2 22 14.1 0.16 46. 112. 0.954 13077 2 23 0.019 13077 2 24 14.1 0.16 47. 111. 1.014 13077 2 25 0.015 13077 2 26 14.1 0.16 47. 113. 0.748 13077 2 27 0.009 13077 2 28 14.1 0.36 48. 115. 0. 1.07 13077 2 29 0.03 13077 2 30 14.9 0.25 46. 109. 1.06 13077 2 31 0.03 13077 2 32 14.9 0.25 46. 112. 0.991 13077 2 33 0.014 13077 2 34 14.9 0.25 47. 111. 1.039 13077 2 35 0.016 13077 2 36 14.9 0.25 47. 113. 0.773 13077 2 37 0.017 13077 2 38 14.9 0.25 48. 115. 0. 1.113 13077 2 39 0.009 13077 2 40 14.9 0.25 63. 156. 0.055 13077 2 41 0.010 13077 2 42 16.3 0.2 46. 109. 0.93 13077 2 43 0.14 13077 2 44 16.3 0.2 46. 112. 1.25 13077 2 45 0.02 13077 2 46 16.3 0.2 47. 111. 1.16 13077 2 47 0.04 13077 2 48 16.3 0.2 47. 113. 0.902 13077 2 49 0.017 13077 2 50 16.3 0.2 48. 115. 0. 1.18 13077 2 51 0.02 13077 2 52 17.3 0.2 46. 109. 1.5 13077 2 53 0.3 13077 2 54 17.3 0.2 46. 112. 1.29 13077 2 55 0.15 13077 2 56 17.3 0.2 47. 111. 1.34 13077 2 57 0.05 13077 2 58 17.3 0.2 47. 113. 1.00 13077 2 59 0.04 13077 2 60 17.3 0.2 55. 136. 0. 0.22 13077 2 61 0.17 13077 2 62 18.1 0.43 46. 109. 1.36 13077 2 63 0.12 13077 2 64 18.1 0.43 46. 112. 1.36 13077 2 65 0.04 13077 2 66 18.1 0.43 47. 111. 1.35 13077 2 67 0.04 13077 2 68 18.1 0.43 47. 113. 1.03 13077 2 69 0.03 13077 2 70 18.1 0.43 48. 115. 0. 1.544 13077 2 71 0.018 13077 2 72 ENDDATA 64 13077 2 73 ENDSUBENT 7 13077 299999 SUBENT 13077003 890518 13077 3 1 BIB 2 2 13077 3 2 REACTION (92-U-238(N,F)ELEM/MASS,CUM,FY) 13077 3 3 SAMPLE ISOTOPIC COMPOSITION OF SAMPLE: 99.9% 238U, 0.1% 235U 13077 3 4 ENDBIB 2 13077 3 5 NOCOMMON 0 0 13077 3 6 DATA 6 21 13077 3 7 EN EN-RSL ELEMENT MASS DATA DATA-ERR 13077 3 8 MEV MEV NO-DIM NO-DIM PC/FIS PC/FIS 13077 3 9 13.4 0.17 46. 109. 1.14 0.12 13077 3 10 13.4 0.17 46. 112. 1.09 0.11 13077 3 11 13.4 0.17 47. 111. 1.07 0.12 13077 3 12 13.4 0.17 47. 113. 0.64 0.07 13077 3 13 13.4 0.17 63. 156. 0.109 0.013 13077 3 14 14.1 0.16 46. 109. 1.20 0.06 13077 3 15 14.1 0.16 46. 112. 1.12 0.05 13077 3 16 14.1 0.16 47. 111. 1.08 0.05 13077 3 17 14.1 0.16 47. 113. 0.66 0.03 13077 3 18 14.1 0.36 63. 156. 0.109 0.008 13077 3 19 14.9 0.25 46. 109. 1.08 0.03 13077 3 20 14.9 0.25 46. 112. 1.09 0.04 13077 3 21 14.9 0.25 47. 111. 1.07 0.03 13077 3 22 14.9 0.25 47. 113. 0.666 0.018 13077 3 23 14.9 0.25 63. 156. 0.109 0.005 13077 3 24 17.3 0.2 46. 109. 1.52 0.12 13077 3 25 17.3 0.2 46. 112. 0.93 0.04 13077 3 26 17.3 0.2 47. 111. 1.12 0.07 13077 3 27 17.3 0.2 47. 113. 0.73 0.03 13077 3 28 18.1 0.43 47. 111. 1.11 0.05 13077 3 29 18.1 0.43 47. 113. 0.86 0.04 13077 3 30 ENDDATA 23 13077 3 31 ENDSUBENT 6 13077 399999 SUBENT 13077004 890518 13077 4 1 BIB 1 1 13077 4 2 REACTION (90-TH-232(N,F)ELEM/MASS,CUM,FY) 13077 4 3 ENDBIB 1 13077 4 4 NOCOMMON 0 0 13077 4 5 DATA 6 19 13077 4 6 EN EN-RSL ELEMENT MASS DATA DATA-ERR 13077 4 7 MEV MEV NO-DIM NO-DIM PC/FIS PC/FIS 13077 4 8 13.4 0.17 46. 109. 1.80 0.09 13077 4 9 13.4 0.17 46. 112. 1.88 0.04 13077 4 10 13.4 0.17 47. 111. 2.06 0.05 13077 4 11 13.4 0.17 47. 113. 1.44 0.02 13077 4 12 13.4 0.17 63. 156. 0.032 0.004 13077 4 13 14.1 0.16 46. 109. 1.61 0.10 13077 4 14 14.1 0.16 46. 112. 1.77 0.02 13077 4 15 14.1 0.16 47. 111. 1.85 0.04 13077 4 16 14.1 0.16 47. 113. 1.34 0.02 13077 4 17 14.1 0.36 63. 156. 0.056 0.007 13077 4 18 14.9 0.25 46. 109. 1.53 0.07 13077 4 19 14.9 0.25 46. 112. 1.71 0.05 13077 4 20 14.9 0.25 47. 111. 1.85 0.06 13077 4 21 14.9 0.25 47. 113. 1.28 0.04 13077 4 22 14.9 0.25 63. 156. 0.044 0.008 13077 4 23 18.1 0.43 46. 109. 2.2 0.3 13077 4 24 18.1 0.43 46. 112. 2.70 0.12 13077 4 25 18.1 0.43 47. 111. 2.52 0.12 13077 4 26 18.1 0.43 47. 113. 1.92 0.10 13077 4 27 ENDDATA 21 13077 4 28 ENDSUBENT 6 13077 499999 ENDENTRY 4 1307799999999 ENTRY 13078 890518 13078 0 1 SUBENT 13078001 890518 13078 1 1 BIB 11 15 13078 1 2 INSTITUTE (1USALRL) 13078 1 3 REFERENCE (J,PR/B,139,1505,6509) 13078 1 4 AUTHOR (D.R.NETHAWAY,H.B.LEVY) 13078 1 5 TITLE EFFECT OF INCREASING EXCITATION ENERGY ON NUCLEAR 13078 1 6 CHARGE DISTRIBUTION IN FISSION 13078 1 7 FACILITY (CCW) 13078 1 8 INC-SOURCE (D-T) 13078 1 9 SAMPLE URANIUM FOILS ENRICHED TO 93% 235U AND URANIUM NITRATE 13078 1 10 HEXAHYDRATE 13078 1 11 METHOD (RCHEM) 13078 1 12 CORRECTION NOT CORRECTED FOR 238U FISSION CONTRIBUTION TO 92Y, 13078 1 13 96NB, 140LA (5%) 13078 1 14 STATUS (RIDER) REFERENCE 65NET1 13078 1 15 (COREL,C0268001) 13078 1 16 HISTORY (890515C) VM 13078 1 17 ENDBIB 15 13078 1 18 COMMON 1 3 13078 1 19 EN 13078 1 20 MEV 13078 1 21 14.9 13078 1 22 ENDCOMMON 1 3 13078 1 23 ENDSUBENT 1 13078 199999 SUBENT 13078002 890518 13078 2 1 BIB 3 5 13078 2 2 REACTION ((92-U-235(N,F)ELEM/MASS,IND,FY)/ 13078 2 3 (92-U-235(N,F)MASS,CHN,FY)) 13078 2 4 RESULT (FRIND) 13078 2 5 ERR-ANALYS DATA UNCERTAINTIES ARE ASSIGNED FROM TABLE VI IN 13078 2 6 PHYS.REV.C 6, 1827 (1972) 13078 2 7 ENDBIB 5 13078 2 8 NOCOMMON 0 0 13078 2 9 DATA 4 5 13078 2 10 ELEMENT MASS DATA DATA-ERR 13078 2 11 NO-DIM NO-DIM NO-DIM NO-DIM 13078 2 12 39. 90. 2.2 -04 0.4 -04 13078 2 13 39. 92. 7.4 -03 1.7 -03 13078 2 14 41. 96. 8.3 -04 13078 2 15 55. 136. 5.8 -02 13078 2 16 57. 140. 7.3 -03 0.5 -03 13078 2 17 ENDDATA 7 13078 2 18 ENDSUBENT 4 13078 299999 ENDENTRY 2 1307899999999 ENTRY 13084 890518 13084 0 1 SUBENT 13084001 890518 13084 1 1 BIB 8 11 13084 1 2 INSTITUTE (1USALAS) 13084 1 3 REFERENCE (J,PR/B,137,929,65) 13084 1 4 AUTHOR (K.WOLFSBERG) 13084 1 5 TITLE NUCLEAR CHARGE DISTRIBUTION IN FISSION: FRACTIONAL 13084 1 6 YIELDS OF KRYPTON AND XENON ISOTOPES FROM THERMAL 13084 1 7 NEUTRON FISSION OF U-233 AND PU-239 AND FROM 14-MEV 13084 1 8 NEUTRON FISSION OF U-235 AND U-238 13084 1 9 METHOD (RCHEM) 13084 1 10 ERR-ANALYS NO INFORMATION 13084 1 11 STATUS (RIDER) REFERENCE 65WOL1 13084 1 12 HISTORY (890515C) VM 13084 1 13 ENDBIB 11 13084 1 14 NOCOMMON 0 0 13084 1 15 ENDSUBENT 0 13084 199999 SUBENT 13084005 890518 13084 5 1 BIB 4 5 13084 5 2 REACTION ((92-U-235(N,F)ELEM/MASS,CUM,FY,,MXW)/ 13084 5 3 (92-U-235(N,F)MASS,CHN,FY,,MXW)) 13084 5 4 RESULT (FRCUM) 13084 5 5 FACILITY (CCW) 13084 5 6 INC-SOURCE (D-T) 13084 5 7 ENDBIB 5 13084 5 8 COMMON 1 3 13084 5 9 EN 13084 5 10 MEV 13084 5 11 14. 13084 5 12 ENDCOMMON 1 3 13084 5 13 DATA 4 7 13084 5 14 ELEMENT MASS DATA DATA-ERR 13084 5 15 NO-DIM NO-DIM NO-DIM NO-DIM 13084 5 16 36. 91. 0.36 0.02 13084 5 17 36. 92. 0.00156 0.00011 13084 5 18 36. 93. 0.039 0.004 13084 5 19 54. 138. 0.75 0.02 13084 5 20 54. 139. 0.429 0.009 13084 5 21 54. 140. 0.204 0.008 13084 5 22 54. 141. 0.056 0.004 13084 5 23 ENDDATA 9 13084 5 24 ENDSUBENT 4 13084 599999 SUBENT 13084006 890518 13084 6 1 BIB 4 5 13084 6 2 REACTION ((92-U-238(N,F)ELEM/MASS,CUM,FY,,MXW)/ 13084 6 3 (92-U-238(N,F)MASS,CHN,FY,,MXW)) 13084 6 4 RESULT (FRCUM) 13084 6 5 FACILITY (CCW) 13084 6 6 INC-SOURCE (D-T) 13084 6 7 ENDBIB 5 13084 6 8 COMMON 1 3 13084 6 9 EN 13084 6 10 MEV 13084 6 11 14. 13084 6 12 ENDCOMMON 1 3 13084 6 13 DATA 4 7 13084 6 14 ELEMENT MASS DATA DATA-ERR 13084 6 15 NO-DIM NO-DIM NO-DIM NO-DIM 13084 6 16 36. 91. 0.65 0.02 13084 6 17 36. 92. 0.44 0.02 13084 6 18 36. 93. 0.164 0.013 13084 6 19 54. 138. 0.94 0.02 13084 6 20 54. 139. 0.805 0.006 13084 6 21 54. 140. 0.611 0.012 13084 6 22 54. 141. 0.29 0.02 13084 6 23 ENDDATA 9 13084 6 24 ENDSUBENT 4 13084 699999 ENDENTRY 3 1308499999999 ENTRY 13087 890518 13087 0 1 SUBENT 13087001 890518 13087 1 1 BIB 11 13 13087 1 2 INSTITUTE (1USAARK) 13087 1 3 REFERENCE (J,JIN,28,2071,66) 13087 1 4 AUTHOR (R.GANAPATHY,P.K.KURODA) 13087 1 5 TITLE MASS DISTRIBUTION IN THE FISSION OF 232TH BY 14.8 MEV 13087 1 6 NEUTRONS 13087 1 7 FACILITY (CCW) 13087 1 8 INC-SOURCE (D-T) 13087 1 9 METHOD (RCHEM) 13087 1 10 DETECTOR (PROPC) 2 PI END-WINDOW LOW-BACKGROUND PROPORTIONAL 13087 1 11 COUNTER 13087 1 12 ERR-ANALYS DATA UNCERTAINTY IS STANDARD DEVIATION 13087 1 13 STATUS (RIDER) REFERENCE 66GAN1 13087 1 14 HISTORY (890516C) VM 13087 1 15 ENDBIB 13 13087 1 16 COMMON 2 3 13087 1 17 EN EN-RSL 13087 1 18 MEV MEV 13087 1 19 14.8 0.2 13087 1 20 ENDCOMMON 2 3 13087 1 21 ENDSUBENT 2 13087 199999 SUBENT 13087002 890518 13087 2 1 BIB 2 3 13087 2 2 REACTION (90-TH-232(N,F)ELEM/MASS,CUM,FY) 13087 2 3 MONITOR (13-AL-27(N,A)11-NA-24,,SIG) 13087 2 4 (90-TH-232(N,F),,SIG) 13087 2 5 ENDBIB 3 13087 2 6 NOCOMMON 0 0 13087 2 7 DATA 4 2 13087 2 8 ELEMENT MASS DATA DATA-ERR 13087 2 9 NO-DIM NO-DIM PC/FIS PC/FIS 13087 2 10 42. 99. 2.00 0.10 13087 2 11 47. 111. 1.50 0.15 13087 2 12 ENDDATA 4 13087 2 13 ENDSUBENT 4 13087 299999 SUBENT 13087003 890518 13087 3 1 BIB 2 2 13087 3 2 REACTION (90-TH-232(N,F)ELEM/MASS,CUM,FY) 13087 3 3 MONITOR (90-TH-232(N,F)42-MO-99,CUM,FY) 13087 3 4 ENDBIB 2 13087 3 5 COMMON 2 3 13087 3 6 MONIT MONIT-ERR 13087 3 7 PC/FIS PC/FIS 13087 3 8 2.00 0.10 13087 3 9 ENDCOMMON 2 3 13087 3 10 DATA 5 6 13087 3 11 ELEMENT MASS ISOMER DATA DATA-ERR 13087 3 12 NO-DIM NO-DIM NO-DIM PC/FIS PC/FIS 13087 3 13 44. 103. 0.75 0.13 13087 3 14 44. 105. 0.92 0.10 13087 3 15 44. 106. 1.07 0.10 13087 3 16 46. 109. 0. 1.10 0.10 13087 3 17 47. 113. 0. 1.20 0.10 13087 3 18 47. 115. 0. 1.24 0.20 13087 3 19 ENDDATA 8 13087 3 20 ENDSUBENT 5 13087 399999 ENDENTRY 3 1308799999999 ENTRY 13089 890907 13089 0 1 SUBENT 13089001 890907 13089 1 1 BIB 11 17 13089 1 2 INSTITUTE (1USAARK) 13089 1 3 REFERENCE (J,JIN,28,3071,66) 13089 1 4 (T,GANAPATHY,68) 13089 1 5 AUTHOR (R.GANAPATHY,H.IHOCHI) 13089 1 6 TITLE YIELDS OF MOLYBDENUM ISOTOPES IN THE FISSION OF TH-232 13089 1 7 AND U-238 BY 14.8 MEV NEUTRONS 13089 1 8 FACILITY (CCW) 13089 1 9 INC-SOURCE (D-T) 13089 1 10 METHOD (RCHEM) 13089 1 11 DETECTOR (PROPC) 2PI END-WINDOW LOW BACKGROUND PROPORTIONAL 13089 1 12 BETA COUNTER 13089 1 13 (NAICR) FOR GAMMA DETECTION 13089 1 14 ERR-ANALYS NO INFORMATION 13089 1 15 STATUS (RIDER) REFERENCE 66GAN3 13089 1 16 HISTORY (890516C) VM 13089 1 17 (890907A) SUPERSEDED STATUS REMOVED 13089 1 18 UPDATED AS PER THESIS 13089 1 19 ENDBIB 17 13089 1 20 COMMON 2 3 13089 1 21 EN EN-RSL 13089 1 22 MEV MEV 13089 1 23 14.8 0.2 13089 1 24 ENDCOMMON 2 3 13089 1 25 ENDSUBENT 2 13089 199999 SUBENT 13089002 890907 13089 2 1 BIB 3 4 13089 2 2 REACTION (90-TH-232(N,F)ELEM/MASS,CUM,FY) 13089 2 3 MONITOR (90-TH-232(N,F)42-MO-99,CUM,FY) 13089 2 4 DECAY-DATA ((1.)42-MO-101,14.6MIN) 13089 2 5 ((2.)42-MO-102,11.MIN) 13089 2 6 ENDBIB 4 13089 2 7 COMMON 2 3 13089 2 8 MONIT MONIT-ERR 13089 2 9 PC/FIS PC/FIS 13089 2 10 2.00 0.20 13089 2 11 ENDCOMMON 2 3 13089 2 12 DATA 5 2 13089 2 13 ELEMENT MASS DATA DATA-ERR DECAY-FLAG 13089 2 14 NO-DIM NO-DIM PC/FIS PC/FIS NO-DIM 13089 2 15 42. 101. 1.60 0.20 1. 13089 2 16 42. 102. 0.70 0.15 2. 13089 2 17 ENDDATA 4 13089 2 18 ENDSUBENT 5 13089 299999 SUBENT 13089003 890907 13089 3 1 BIB 3 4 13089 3 2 REACTION (92-U-238(N,F)42-MO-99,CUM,FY) 13089 3 3 MONITOR (13-AL-27(N,A)11-NA-24,,SIG) 13089 3 4 (92-U-238(N,F),,SIG) 13089 3 5 DECAY-DATA (42-MO-99,66.HR) 13089 3 6 ENDBIB 4 13089 3 7 NOCOMMON 0 0 13089 3 8 DATA 2 1 13089 3 9 DATA DATA-ERR 13089 3 10 PC/FIS PC/FIS 13089 3 11 5.60 0.28 13089 3 12 ENDDATA 3 13089 3 13 ENDSUBENT 2 13089 399999 SUBENT 13089004 890907 13089 4 1 BIB 3 4 13089 4 2 REACTION (92-U-238(N,F)ELEM/MASS,CUM,FY) 13089 4 3 MONITOR (92-U-238(N,F)42-MO-99,CUM,FY) 13089 4 4 DECAY-DATA ((1.)42-MO-101,14.6MIN) 13089 4 5 ((2.)42-MO-102,11.MIN) 13089 4 6 ENDBIB 4 13089 4 7 COMMON 2 3 13089 4 8 MONIT MONIT-ERR 13089 4 9 PC/FIS PC/FIS 13089 4 10 5.60 0.28 13089 4 11 ENDCOMMON 2 3 13089 4 12 DATA 5 2 13089 4 13 ELEMENT MASS DATA DATA-ERR DECAY-FLAG 13089 4 14 NO-DIM NO-DIM PC/FIS PC/FIS NO-DIM 13089 4 15 42. 101. 6.35 0.30 1. 13089 4 16 42. 102. 2.85 0.30 2. 13089 4 17 ENDDATA 4 13089 4 18 ENDSUBENT 5 13089 499999 SUBENT 13089005 890907 13089 5 1 BIB 4 5 13089 5 2 REACTION (90-TH-232(N,F)42-MO-99,CUM,FY) 13089 5 3 MONITOR (13-AL-27(N,A)11-NA-24,,SIG) 13089 5 4 (90-TH-232(N,F),,SIG) 13089 5 5 DECAY-DATA (42-MO-99,66.HR) 13089 5 6 HISTORY (890907C) 13089 5 7 ENDBIB 5 13089 5 8 NOCOMMON 0 0 13089 5 9 DATA 2 1 13089 5 10 DATA DATA-ERR 13089 5 11 PC/FIS PC/FIS 13089 5 12 2.00 0.20 13089 5 13 ENDDATA 3 13089 5 14 ENDSUBENT 2 13089 599999 ENDENTRY 5 1308999999999 ENTRY 13091 900326 13091 0 1 SUBENT 13091001 890518 13091 1 1 BIB 10 12 13091 1 2 INSTITUTE (1USALRL) 13091 1 3 REFERENCE (J,PR,128,700,6210) 13091 1 4 AUTHOR (H.G.HICKS,H.B.LEVY,W.E.NERVIK,P.C.STEVENSON, 13091 1 5 J.B.NIDAY,J.C.ARMSTRONG JR) 13091 1 6 TITLE FURTHER RADIOCHEMICAL STUDIES OF THE U236* COMPOUND 13091 1 7 NUCLEUS 13091 1 8 FACILITY (CCW) 13091 1 9 INC-SOURCE (D-T) 13091 1 10 METHOD (RCHEM) 13091 1 11 ERR-ANALYS DATA UNCERTAINTY IS STANDARD DEVIATION 13091 1 12 STATUS (RIDER) REFERENCE 62HIC1 13091 1 13 HISTORY (890516C) VM 13091 1 14 ENDBIB 12 13091 1 15 NOCOMMON 0 0 13091 1 16 ENDSUBENT 0 13091 199999 SUBENT 13091002 900326 13091 2 1 BIB 3 7 13091 2 2 REACTION (((92-U-235(N,F)ELEM/MASS,CUM,FY)/ 13091 2 3 (92-U-235(N,F)42-MO-99,CUM,FY))// 13091 2 4 ((92-U-235(N,F)ELEM/MASS,CUM,FY,,MXW)/ 13091 2 5 (92-U-235(N,F)42-MO-99,CUM,FY,,MXW))) 13091 2 6 RESULT (RVAL) 13091 2 7 HISTORY (900326A) SUBENTRY NUMBER CHANGED FROM 13091016, 13091 2 8 DATA CORRECTED 13091 2 9 ENDBIB 7 13091 2 10 COMMON 2 3 13091 2 11 EN-NM EN-DUM-DN 13091 2 12 MEV EV 13091 2 13 14. 0.0253 13091 2 14 ENDCOMMON 2 3 13091 2 15 DATA 5 17 13091 2 16 ELEMENT MASS ISOMER DATA DATA-ERR 13091 2 17 NO-DIM NO-DIM NO-DIM NO-DIM PER-CENT 13091 2 18 30. 72. 220. 10. 13091 2 19 38. 89. 0.97 5. 13091 2 20 39. 91. 0. 0.98 5. 13091 2 21 40. 95. 0.98 5. 13091 2 22 40. 97. 1.01 5. 13091 2 23 46. 109. 0. 53. 5. 13091 2 24 46. 112. 86. 5. 13091 2 25 47. 111. 0. 81. 5. 13091 2 26 48. 115. 0. 103. 5. 13091 2 27 55. 136. 0. 46. 5. 13091 2 28 56. 140. 0.96 5. 13091 2 29 58. 141. 0.95 5. 13091 2 30 58. 144. 0.86 5. 13091 2 31 60. 147. 0.90 5. 13091 2 32 62. 153. 1.93 5. 13091 2 33 63. 156. 5.1 5. 13091 2 34 65. 161. 94. 10. 13091 2 35 ENDDATA 19 13091 2 36 ENDSUBENT 5 13091 299999 ENDENTRY 2 1309199999999 ENTRY 13095 900326 13095 0 1 SUBENT 13095001 890518 13095 1 1 BIB 12 14 13095 1 2 INSTITUTE (1USAARK) 13095 1 3 REFERENCE (J,PR/B,133,874,6402) 13095 1 4 AUTHOR (K.M.BROOM) 13095 1 5 TITLE 2.95-MEV AND 14.8 MEV NEUTRON-INDUCED FISSION OF TH232 13095 1 6 FACILITY (CCW) 13095 1 7 INC-SOURCE (D-T) 13095 1 8 SAMPLE REAGENT GRADE THORIUM NITRATE 13095 1 9 METHOD (RCHEM) 13095 1 10 DETECTOR (PROPC) 2 PI END-WINDOW METHANE-FLOW PORPORTIONAL 13095 1 11 COUNTER FOR GROSS BETA COUNTING 13095 1 12 (NAICR) NAI(TL) DETECTORS FOR GAMMA-RAYS 13095 1 13 ERR-ANALYS DATA UNCERTAINTIES ARE MOST PROBABLE ERRORS 13095 1 14 STATUS (RIDER) REFERENCE 64BRO1 13095 1 15 HISTORY (890516C) VM 13095 1 16 ENDBIB 14 13095 1 17 NOCOMMON 0 0 13095 1 18 ENDSUBENT 0 13095 199999 SUBENT 13095002 890518 13095 2 1 BIB 2 2 13095 2 2 REACTION (90-TH-232(N,F)42-MO-99,CUM,FY) 13095 2 3 MONITOR (13-AL-27(N,A)11-NA-24,,SIG) 13095 2 4 ENDBIB 2 13095 2 5 NOCOMMON 0 0 13095 2 6 DATA 5 1 13095 2 7 EN EN-RSL DATA DATA-ERR MONIT 13095 2 8 MEV MEV PC/FIS PC/FIS MB 13095 2 9 14.8 0.02 1.96 0.15 115. 13095 2 10 ENDDATA 3 13095 2 11 ENDSUBENT 5 13095 299999 SUBENT 13095005 900326 13095 5 1 BIB 3 3 13095 5 2 REACTION (90-TH-232(N,F)ELEM/MASS,CUM,FY) 13095 5 3 MONITOR (90-TH-232(N,F)42-MO-99,CUM,FY) 13095 5 4 HISTORY (900326A) DATA CORRECTED 13095 5 5 ENDBIB 3 13095 5 6 COMMON 4 3 13095 5 7 EN EN-RSL MONIT MONIT-ERR 13095 5 8 MEV MEV PC/FIS PC/FIS 13095 5 9 14.8 0.02 1.96 0.15 13095 5 10 ENDCOMMON 4 3 13095 5 11 DATA 5 15 13095 5 12 MASS ELEMENT ISOMER DATA DATA-ERR 13095 5 13 NO-DIM NO-DIM NO-DIM PC/FIS PC/FIS 13095 5 14 89. 38. 6.03 0.48 13095 5 15 90. 38. 5.72 0.81 13095 5 16 91. 38. 5.52 0.52 13095 5 17 92. 38. 5.58 0.53 13095 5 18 111. 47. 0. 1.13 0.11 13095 5 19 112. 47. 1.32 0.17 13095 5 20 113. 47. 0. 1.10 0.08 13095 5 21 115. 47. 0. 1.72 0.50 13095 5 22 131. 53. 1.59 0.21 13095 5 23 132. 53. 0. 3.10 0.15 13095 5 24 133. 53. 0. 3.78 0.18 13095 5 25 134. 53. 0. 6.69 0.36 13095 5 26 135. 53. 4.74 0.24 13095 5 27 139. 56. 5.34 0.37 13095 5 28 140. 56. 5.97 0.35 13095 5 29 ENDDATA 17 13095 5 30 ENDSUBENT 5 13095 599999 ENDENTRY 3 1309599999999 ENTRY 13116 891122 13116 0 1 SUBENT 13116001 891122 13116 1 1 BIB 14 18 13116 1 2 INSTITUTE (1USALRL) 13116 1 3 REFERENCE (P,UCAR-10062-83/1,64,8301) 13116 1 4 AUTHOR (D.R.NETHAWAY,F.F.MOMYER) 13116 1 5 TITLE MEASUREMENT OF 14-MEV FISSION YIELDS 13116 1 6 FACILITY RTNS-II 13116 1 7 INC-SOURCE (D-T) 13116 1 8 SAMPLE METAL TARGETS 13116 1 9 METHOD (RCHEM) 13116 1 10 DETECTOR (GELI) 13116 1 11 MONITOR RELATIVE TO 95ZR, 99MO, 144CE AND 147ND YIELDS. 13116 1 12 DECAY-DATA ((1.)36-KR-85,10.76YR,DG,514.0,0.00435) 13116 1 13 ((2.)63-EU-156,15.14D,DG,811.8,0.1012,DG,1153.8,0.1208)13116 1 14 ((3.)65-TB-161,6.91D,DG,74.6,0.123) 13116 1 15 ERR-ANALYS STATISTICAL UNCERTAINTIES ARE ABOUT 1% AND DO 13116 1 16 NOT INCLUDE UNCERTAINTY IN DECAY SCHEME OR NUMBER OF 13116 1 17 FISSION 13116 1 18 STATUS (APRVD) D.R.NETHAWAY, 89/11/20. 13116 1 19 HISTORY (891103C) 13116 1 20 ENDBIB 18 13116 1 21 COMMON 1 3 13116 1 22 ERR-S 13116 1 23 PER-CENT 13116 1 24 1. 13116 1 25 ENDCOMMON 1 3 13116 1 26 ENDSUBENT 1 13116 199999 SUBENT 13116002 891122 13116 2 1 BIB 2 3 13116 2 2 REACTION (92-U-235(N,F)ELEM/MASS,CUM,FY,,REL) 13116 2 3 DATA GIVEN AS NUCLEI/FISSION 13116 2 4 SAMPLE ORALLOY SAMPLE 13116 2 5 ENDBIB 3 13116 2 6 NOCOMMON 0 0 13116 2 7 DATA 5 6 13116 2 8 EN ELEMENT MASS DATA DECAY-FLAG 13116 2 9 MEV NO-DIM NO-DIM NO-DIM NO-DIM 13116 2 10 14.3 36. 85. 3.98 -03 1. 13116 2 11 14.3 63. 156. 5.14 -04 2. 13116 2 12 14.3 65. 161. 4.09 -05 3. 13116 2 13 14.7 36. 85. 4.00 -03 1. 13116 2 14 14.7 63. 156. 5.35 -04 2. 13116 2 15 14.7 65. 161. 4.38 -05 3. 13116 2 16 ENDDATA 8 13116 2 17 ENDSUBENT 5 13116 299999 SUBENT 13116003 891122 13116 3 1 BIB 1 2 13116 3 2 REACTION (92-U-238(N,F)ELEM/MASS,CUM,FY,,REL) 13116 3 3 DATA GIVEN AS NUCLEI/FISSION 13116 3 4 ENDBIB 2 13116 3 5 NOCOMMON 0 0 13116 3 6 DATA 5 3 13116 3 7 EN ELEMENT MASS DATA DECAY-FLAG 13116 3 8 MEV NO-DIM NO-DIM NO-DIM NO-DIM 13116 3 9 14.4 36. 85. 2.50 -03 1. 13116 3 10 14.4 63. 156. 1.04 -03 2. 13116 3 11 14.4 65. 161. 6.89 -05 3. 13116 3 12 ENDDATA 5 13116 3 13 ENDSUBENT 5 13116 399999 SUBENT 13116004 891122 13116 4 1 BIB 2 3 13116 4 2 REACTION (94-PU-239(N,F)ELEM/MASS,CUM,FY,,REL) 13116 4 3 DATA GIVEN AS NUCLEI/FISSION 13116 4 4 SAMPLE WEAPONS GRADE PLUTONIUM 13116 4 5 ENDBIB 3 13116 4 6 NOCOMMON 0 0 13116 4 7 DATA 5 3 13116 4 8 EN ELEMENT MASS DATA DECAY-FLAG 13116 4 9 MEV NO-DIM NO-DIM NO-DIM NO-DIM 13116 4 10 14.8 36. 85. 2.32 -03 1. 13116 4 11 14.8 63. 156. 1.94 -03 2. 13116 4 12 14.8 65. 161. 2.29 -04 3. 13116 4 13 ENDDATA 5 13116 4 14 ENDSUBENT 5 13116 499999 ENDENTRY 4 1311699999999 ENTRY 13223 881102 13223 0 1 SUBENT 13223001 881102 13223 1 1 BIB 11 12 13223 1 2 INSTITUTE (1USAARK) 13223 1 3 REFERENCE (J,JIN,26,401,64) 13223 1 4 AUTHOR (M.P.MENON,P.K.KURODA) 13223 1 5 TITLE SPONTANEOUS AND 14.7 MEV NEUTRON INDUCED FISSION 13223 1 6 YIELDS OF URANIUM-238 IN THE RARE EARTH REGION 13223 1 7 FACILITY (CCW) 13223 1 8 INC-SOURCE (D-T) 13223 1 9 METHOD (RCHEM) 13223 1 10 DETECTOR (GEMUC) 13223 1 11 ERR-ANALYS NO INFORMATION 13223 1 12 STATUS (RIDER) REFERENCE 64MEN1 13223 1 13 HISTORY (890524C) VM 13223 1 14 ENDBIB 12 13223 1 15 NOCOMMON 0 0 13223 1 16 ENDSUBENT 0 13223 199999 SUBENT 13223002 881102 13223 2 1 BIB 4 4 13223 2 2 REACTION (92-U-238(N,F)ELEM/MASS,CUM,FY) 13223 2 3 SAMPLE DEPLETED URANIUM, ISOTOPIC COMPOSITION 99.989% 238U. 13223 2 4 MONITOR (92-U-238(N,F)56-BA-140,CUM,FY) 13223 2 5 MONIT-REF (,BROOM,J,PR,126,627,62) 13223 2 6 ENDBIB 4 13223 2 7 COMMON 3 3 13223 2 8 EN MONIT MONIT-ERR 13223 2 9 MEV PC/FIS PC/FIS 13223 2 10 14.7 4.3 0.4 13223 2 11 ENDCOMMON 3 3 13223 2 12 DATA 4 4 13223 2 13 ELEMENT MASS DATA DATA-ERR 13223 2 14 NO-DIM NO-DIM PC/FIS PC/FIS 13223 2 15 58. 141. 3.9 0.4 13223 2 16 58. 143. 4.3 0.5 13223 2 17 58. 144. 4. 2. 13223 2 18 61. 147. 2.3 0.3 13223 2 19 ENDDATA 6 13223 2 20 ENDSUBENT 4 13223 299999 ENDENTRY 2 1322399999999 ENTRY 13233 931228 13233 0 1 SUBENT 13233001 931228 13233 1 1 BIB 7 10 13233 1 2 INSTITUTE (1CANMCM) 13233 1 3 REFERENCE (J,CJC,46,1663,68) 13233 1 4 AUTHOR (D.J.GORMAN,R.H.TOMLINSON) 13233 1 5 TITLE Cumulative yields in the 14-MeV neutron fission of 13233 1 6 U-238 13233 1 7 ERR-ANALYS Data uncertainties given are standard deviations 13233 1 8 STATUS (RIDER) REFERENCE 68GOR1 13233 1 9 HISTORY (890606C) VM 13233 1 10 (931228A) Energy moved to subentries, converted to 13233 1 11 lower case 13233 1 12 ENDBIB 10 13233 1 13 NOCOMMON 0 0 13233 1 14 ENDSUBENT 0 13233 199999 SUBENT 13233002 931228 13233 2 1 BIB 4 6 13233 2 2 REACTION ((92-U-238(N,F)ELEM/MASS,CUM,FY)/ 13233 2 3 (92-U-238(N,F)36-KR-86,CUM,FY)) 13233 2 4 SAMPLE U-Cl(4) 13233 2 5 METHOD (ASEP) 13233 2 6 CORRECTION 85Kr corrected for decay assuming 10.6yr T1/2 for g.s.,13233 2 7 and that 22.5% of the 4.4hr isomer decays to g.s. 13233 2 8 ENDBIB 6 13233 2 9 COMMON 1 3 13233 2 10 EN 13233 2 11 EV 13233 2 12 14. E+06 13233 2 13 ENDCOMMON 1 3 13233 2 14 DATA 4 3 13233 2 15 ELEMENT MASS DATA DATA-ERR 13233 2 16 NO-DIM NO-DIM NO-DIM NO-DIM 13233 2 17 36. 83. 0.423 0.004 13233 2 18 36. 84. 0.716 0.007 13233 2 19 36. 85. 0.635 0.006 13233 2 20 ENDDATA 5 13233 2 21 ENDSUBENT 4 13233 299999 SUBENT 13233003 931228 13233 3 1 BIB 3 4 13233 3 2 REACTION ((92-U-238(N,F)ELEM/MASS,CUM,FY)/ 13233 3 3 (92-U-238(N,F)54-XE-134,CUM,FY)) 13233 3 4 SAMPLE U-Cl(4) 13233 3 5 METHOD (ASEP) 13233 3 6 ENDBIB 4 13233 3 7 COMMON 1 3 13233 3 8 EN 13233 3 9 EV 13233 3 10 14. E+06 13233 3 11 ENDCOMMON 1 3 13233 3 12 DATA 4 5 13233 3 13 ELEMENT MASS DATA DATA-ERR 13233 3 14 NO-DIM NO-DIM NO-DIM NO-DIM 13233 3 15 54. 131. 0.618 0.002 13233 3 16 54. 132. 0.760 0.004 13233 3 17 54. 133. 0.935 0.001 13233 3 18 54. 135. 0.906 0.016 13233 3 19 54. 136. 0.883 .003 13233 3 20 ENDDATA 7 13233 3 21 ENDSUBENT 4 13233 399999 SUBENT 13233004 931228 13233 4 1 BIB 4 5 13233 4 2 REACTION ((92-U-238(N,F)55-CS-137,CUM,FY)/ 13233 4 3 (92-U-238(N,F)55-CS-135,CUM,FY)) 13233 4 4 SAMPLE U-F(6) 13233 4 5 METHOD (ASEP) 13233 4 6 DECAY-DATA (55-CS-137,30.4YR) 13233 4 7 ENDBIB 5 13233 4 8 COMMON 1 3 13233 4 9 EN 13233 4 10 EV 13233 4 11 14. E+06 13233 4 12 ENDCOMMON 1 3 13233 4 13 DATA 2 1 13233 4 14 DATA DATA-ERR 13233 4 15 NO-DIM NO-DIM 13233 4 16 0.863 0.086 13233 4 17 ENDDATA 3 13233 4 18 ENDSUBENT 2 13233 499999 SUBENT 13233005 931228 13233 5 1 BIB 3 6 13233 5 2 REACTION (((92-U-238(N,F)ELEM/MASS,CUM,FY)/ 13233 5 3 (92-U-238(N,F)43-TC-99,CUM,FY))// 13233 5 4 ((92-U-235(N,F)ELEM/MASS,CUM,FY,,MXW)/ 13233 5 5 (92-U-235(N,F)43-TC-99,CUM,FY,,MXW))) 13233 5 6 RESULT (RVAL) 13233 5 7 METHOD (RCHEM) 13233 5 8 ENDBIB 6 13233 5 9 COMMON 2 3 13233 5 10 EN-NM EN-DUM-DN 13233 5 11 MEV EV 13233 5 12 14. 0.0253 13233 5 13 ENDCOMMON 2 3 13233 5 14 DATA 4 11 13233 5 15 ELEMENT MASS DATA DATA-ERR 13233 5 16 NO-DIM NO-DIM NO-DIM NO-DIM 13233 5 17 36. 85. 0.944 0.033 13233 5 18 39. 91. 0.691 0.045 13233 5 19 40. 97. 0.954 0.062 13233 5 20 44. 103. 1.89 0.24 13233 5 21 53. 131. 1.46 0.14 13233 5 22 53. 132. 1.10 0.12 13233 5 23 53. 133. 1.01 0.08 13233 5 24 54. 135. 1.04 0.06 13233 5 25 56. 139. 0.861 0.041 13233 5 26 56. 140. 0.800 0.087 13233 5 27 58. 143. 0.822 0.076 13233 5 28 ENDDATA 13 13233 5 29 ENDSUBENT 4 13233 599999 SUBENT 13233006 931228 13233 6 1 BIB 4 7 13233 6 2 REACTION (((92-U-238(N,F)ELEM/MASS,CUM,FY)/ 13233 6 3 (92-U-238(N,F)58-CE-143,CUM,FY))// 13233 6 4 ((92-U-235(N,F)ELEM/MASS,CUM,FY,,MXW)/ 13233 6 5 (92-U-235(N,F)58-CE-143,CUM,FY,,MXW))) 13233 6 6 RESULT (RVAL) 13233 6 7 METHOD (RCHEM) 13233 6 8 HISTORY (931228A) REACTION corrected 13233 6 9 ENDBIB 7 13233 6 10 COMMON 2 3 13233 6 11 EN-NM EN-DUM-DN 13233 6 12 MEV EV 13233 6 13 14. 0.0253 13233 6 14 ENDCOMMON 2 3 13233 6 15 DATA 4 2 13233 6 16 ELEMENT MASS DATA DATA-ERR 13233 6 17 NO-DIM NO-DIM NO-DIM NO-DIM 13233 6 18 58. 141. 1.14 0.04 13233 6 19 60. 147. 1.26 0.07 13233 6 20 ENDDATA 4 13233 6 21 ENDSUBENT 4 13233 699999 SUBENT 13233007 931228 13233 7 1 BIB 3 4 13233 7 2 REACTION (92-U-238(N,F)MASS,CHN,FY) 13233 7 3 METHOD (RCHEM) 13233 7 4 MONITOR (92-U-238(N,F)MASS,CHN,FY) Relative to mass 134, 13233 7 5 normalized to heavy peak. 13233 7 6 ENDBIB 4 13233 7 7 COMMON 2 3 13233 7 8 EN MASS-NRM 13233 7 9 MEV NO-DIM 13233 7 10 14. 134. 13233 7 11 ENDCOMMON 2 3 13233 7 12 DATA 3 8 13233 7 13 MASS DATA DATA-ERR 13233 7 14 NO-DIM PC/FIS PC/FIS 13233 7 15 83. 0.748 0.043 13233 7 16 84. 1.26 0.10 13233 7 17 85. 1.12 0.06 13233 7 18 86. 1.76 0.10 13233 7 19 91. 3.66 0.29 13233 7 20 97. 5.27 0.41 13233 7 21 99. 5.50 0.24 13233 7 22 103. 5.15 0.69 13233 7 23 ENDDATA 10 13233 7 24 ENDSUBENT 3 13233 799999 SUBENT 13233008 931228 13233 8 1 BIB 4 7 13233 8 2 REACTION (92-U-238(N,F)MASS,CHN,FY) 13233 8 3 METHOD (RCHEM) 13233 8 4 ANALYSIS Assumed yields for 119-130 = 15.98%, 138 = 5.04%, 13233 8 5 142 = 4.55%, 144 = 3.57%, 145 = 2.99%, 146 = 2.40%, 13233 8 6 148-157 = 6.53%. 13233 8 7 MONITOR (92-U-238(N,F)MASS,CHN,FY) Relative to mass 134, 13233 8 8 normalized so that yields add to 100% 13233 8 9 ENDBIB 7 13233 8 10 COMMON 2 3 13233 8 11 EN MASS-NRM 13233 8 12 MEV NO-DIM 13233 8 13 14. 134. 13233 8 14 ENDCOMMON 2 3 13233 8 15 DATA 3 12 13233 8 16 MASS DATA DATA-ERR 13233 8 17 NO-DIM PC/FIS PC/FIS 13233 8 18 131. 4.02 0.09 13233 8 19 132. 4.94 0.11 13233 8 20 133. 6.08 0.14 13233 8 21 134. 6.50 0.15 13233 8 22 135. 5.89 0.17 13233 8 23 136. 5.74 0.13 13233 8 24 137. 5.08 0.52 13233 8 25 139. 5.02 0.33 13233 8 26 140. 4.54 0.53 13233 8 27 141. 4.84 0.39 13233 8 28 143. 4.26 0.44 13233 8 29 147. 2.03 0.24 13233 8 30 ENDDATA 14 13233 8 31 ENDSUBENT 3 13233 899999 ENDENTRY 8 1323399999999 ENTRY 13235 881102 13235 0 1 SUBENT 13235001 881102 13235 1 1 BIB 12 14 13235 1 2 INSTITUTE (1USAARK) 13235 1 3 REFERENCE (J,JIN,30,345,6802) 13235 1 4 REPLACES ORO-3235-12, PAGE 19 (JANUARY 31, 1967) 13235 1 5 AUTHOR (T.MO,M.N.RAO) 13235 1 6 TITLE SYMMETRIC FISSION OF 232TH BY 14 MEV NEUTRONS 13235 1 7 FACILITY (CCW) 13235 1 8 INC-SOURCE (D-T) 13235 1 9 SAMPLE THORIUM CARBONATE 13235 1 10 METHOD (RCHEM) 13235 1 11 DETECTOR (PROPC) 2PI END-WINDOW BETA PROPORTIONAL COUNTER 13235 1 12 (NAICR) GAMMA DETECTOR 13235 1 13 ERR-ANALYS DATA UNCERTAINTIES GIVEN ARE STANDARD DEVIATIONS 13235 1 14 STATUS (RIDER) REFERENCE 68MO 1 13235 1 15 HISTORY (890607C) VM 13235 1 16 ENDBIB 14 13235 1 17 COMMON 1 3 13235 1 18 EN 13235 1 19 MEV 13235 1 20 14.8 13235 1 21 ENDCOMMON 1 3 13235 1 22 ENDSUBENT 1 13235 199999 SUBENT 13235002 881102 13235 2 1 BIB 2 2 13235 2 2 REACTION (90-TH-232(N,F)42-MO-99,CUM,FY) 13235 2 3 MONITOR (13-AL-27(N,A)11-NA-24,,SIG) FLUX MONITOR 13235 2 4 ENDBIB 2 13235 2 5 NOCOMMON 0 0 13235 2 6 DATA 2 1 13235 2 7 DATA DATA-ERR 13235 2 8 PC/FIS PC/FIS 13235 2 9 2.0 0.1 13235 2 10 ENDDATA 3 13235 2 11 ENDSUBENT 2 13235 299999 SUBENT 13235003 881102 13235 3 1 BIB 3 5 13235 3 2 REACTION (90-TH-232(N,F)ELEM/MASS,CUM,FY) 13235 3 3 MONITOR (90-TH-232(N,F)42-MO-99,CUM,FY) 13235 3 4 COMMENT AUTHORS GIVE VALUE FOR 129(M)TE. AS PER CROUCH, 13235 3 5 AT.DATA & NUCL.DATA TABLES 19, 417 (1977), VALUE 13235 3 6 ASSIGNED TO 70 MINUTE G.S. ISOMER 13235 3 7 ENDBIB 5 13235 3 8 COMMON 2 3 13235 3 9 MONIT MONIT-ERR 13235 3 10 PC/FIS PC/FIS 13235 3 11 2.0 0.1 13235 3 12 ENDCOMMON 2 3 13235 3 13 DATA 5 6 13235 3 14 ELEMENT MASS ISOMER DATA DATA-ERR 13235 3 15 NO-DIM NO-DIM NO-DIM PC/FIS PC/FIS 13235 3 16 48. 115. 0. 1.5 0.2 13235 3 17 50. 121. 0. 1.0 0.1 13235 3 18 50. 125. 0. 0.58 0.1 13235 3 19 51. 127. 1.21 0.2 13235 3 20 52. 129. 0. 1.6 0.1 13235 3 21 52. 132. 2.2 0.2 13235 3 22 ENDDATA 8 13235 3 23 ENDSUBENT 5 13235 399999 ENDENTRY 3 1323599999999 ENTRY 13238 900326 13238 0 1 SUBENT 13238001 881102 13238 1 1 BIB 14 17 13238 1 2 INSTITUTE (1USAARK) 13238 1 3 REFERENCE (J,JIN,30,1145,6806) 13238 1 4 (J,DA/B,29,1809,68) THESIS, THEIN, 1968 13238 1 5 AUTHOR (M.THEIN,M.N.RAO,P.K.KURODA) 13238 1 6 TITLE MASS DISTRIBUTION IN 14.8 MEV NEUTRON-INDUCED FISSION 13238 1 7 OF 232TH 13238 1 8 FACILITY (CCW) 13238 1 9 INC-SOURCE (D-T) 13238 1 10 SAMPLE THORIUM CARBONATE 13238 1 11 METHOD (RCHEM) 13238 1 12 DETECTOR (PROPC) 2PI END-WINDOW BETA PROPORTIONAL COUNTER 13238 1 13 (NAICR) GAMMA DETECTOR 13238 1 14 MONITOR (90-TH-232(N,F)42-MO-99,CUM,FY) 13238 1 15 DECAY-MON (42-MO-99,66.HR) 13238 1 16 ERR-ANALYS DATA UNCERTAINTIES GIVEN ARE STATISTICAL ERRORS 13238 1 17 STATUS (RIDER) REFERENCE 68THE1 13238 1 18 HISTORY (890607C) VM 13238 1 19 ENDBIB 17 13238 1 20 COMMON 4 3 13238 1 21 EN EN-RSL MONIT MONIT-ERR 13238 1 22 MEV MEV PC/FIS PC/FIS 13238 1 23 14.8 0.2 2.0 0.1 13238 1 24 ENDCOMMON 4 3 13238 1 25 ENDSUBENT 4 13238 199999 SUBENT 13238002 900326 13238 2 1 BIB 3 16 13238 2 2 REACTION (90-TH-232(N,F)ELEM/MASS,CUM,FY) 13238 2 3 DECAY-DATA ((1.)39-Y-91,59.D) 13238 2 4 ((2.)39-Y-93,10.1HR) 13238 2 5 ((3.)58-CE-141,32.5D) 13238 2 6 ((4.)58-CE-143,33.HR) 13238 2 7 ((4.)59-PR-143,13.7D) 13238 2 8 ((5.)58-CE-144,285.D) 13238 2 9 ((6.)59-PR-145,5.9HR) 13238 2 10 ((7.)60-ND-147,11.1D) 13238 2 11 ((8.)61-PM-149,53.HR) 13238 2 12 ((9.)61-PM-151,28.HR) 13238 2 13 ((10.)62-SM-153,47.HR) 13238 2 14 ((11.)62-SM-156,9.4HR) 13238 2 15 ((11.)63-EU-156,15.2D) 13238 2 16 ((12.)63-EU-157,15.2HR) 13238 2 17 HISTORY (900326A) BIB CORRECTION 13238 2 18 ENDBIB 16 13238 2 19 NOCOMMON 0 0 13238 2 20 DATA 5 12 13238 2 21 ELEMENT MASS DATA DATA-ERR DECAY-FLAG 13238 2 22 NO-DIM NO-DIM PC/FIS PC/FIS NO-DIM 13238 2 23 39. 91. 5.94 0.60 1. 13238 2 24 39. 93. 5.76 0.60 2. 13238 2 25 58. 141. 5.78 0.70 3. 13238 2 26 58. 144. 5.12 1.54 5. 13238 2 27 59. 143. 5.26 0.50 4. 13238 2 28 59. 145. 5.06 0.50 6. 13238 2 29 60. 147. 1.70 0.12 7. 13238 2 30 61. 149. 0.66 0.07 8. 13238 2 31 61. 151. 0.16 0.03 9. 13238 2 32 62. 153. 0.085 0.010 10. 13238 2 33 63. 156. 0.036 0.007 11. 13238 2 34 63. 157. 0.012 0.006 12. 13238 2 35 ENDDATA 14 13238 2 36 ENDSUBENT 5 13238 299999 ENDENTRY 2 1323899999999 ENTRY 13243 881102 13243 0 1 SUBENT 13243001 881102 13243 1 1 BIB 12 14 13243 1 2 INSTITUTE (1USAARK) 13243 1 3 REFERENCE (J,JIN,31,2623,6908) 13243 1 4 (J,DA/B,29,1621,6811) 13243 1 5 AUTHOR (K.D.BORDEN,P.K.KURODA) 13243 1 6 TITLE MASS DISTRIBUTION IN THE FISSION OF 233U BY 14.8 MEV 13243 1 7 NEUTRONS 13243 1 8 FACILITY (CCW) 13243 1 9 INC-SOURCE (D-T) 13243 1 10 METHOD (RCHEM) 13243 1 11 DETECTOR TRACERLAB OMNI-GUARD LOW BACKGROUND BETA COUNTERS 13243 1 12 MONITOR (92-U-233(N,F)56-BA-140,CUM,FY) 13243 1 13 ERR-ANALYS NO INFORMATION ON SOURCE OF DATA UNCERTAINTY GIVEN 13243 1 14 STATUS (RIDER) REFERENCE 69BOR1 13243 1 15 HISTORY (890607C) VM 13243 1 16 ENDBIB 14 13243 1 17 COMMON 2 3 13243 1 18 EN MONIT 13243 1 19 MEV PC/FIS 13243 1 20 14.8 5.60 13243 1 21 ENDCOMMON 2 3 13243 1 22 ENDSUBENT 2 13243 199999 SUBENT 13243002 881102 13243 2 1 BIB 1 1 13243 2 2 REACTION (92-U-233(N,F)ELEM/MASS,CUM,FY) 13243 2 3 ENDBIB 1 13243 2 4 NOCOMMON 0 0 13243 2 5 DATA 4 21 13243 2 6 ELEMENT MASS DATA DATA-ERR 13243 2 7 NO-DIM NO-DIM PC/FIS PC/FIS 13243 2 8 35. 83. 1.33 0.08 13243 2 9 35. 84. 2.02 0.10 13243 2 10 38. 89. 4.82 0.50 13243 2 11 38. 91. 5.65 0.35 13243 2 12 38. 92. 5.72 0.37 13243 2 13 42. 99. 3.64 0.20 13243 2 14 44. 105. 1.63 0.20 13243 2 15 46. 109. 1.20 0.12 13243 2 16 47. 111. 1.21 0.15 13243 2 17 47. 112. 1.08 0.10 13243 2 18 47. 113. 1.06 0.11 13243 2 19 49. 115. 1.03 0.13 13243 2 20 50. 121. 1.06 0.07 13243 2 21 50. 125. 1.51 0.09 13243 2 22 51. 127. 2.20 0.12 13243 2 23 53. 131. 3.40 0.25 13243 2 24 53. 132. 3.95 0.30 13243 2 25 53. 133. 4.36 0.32 13243 2 26 53. 134. 4.65 0.35 13243 2 27 54. 135. 4.96 0.36 13243 2 28 56. 139. 5.79 0.24 13243 2 29 ENDDATA 23 13243 2 30 ENDSUBENT 4 13243 299999 ENDENTRY 2 1324399999999 ENTRY 13251 881102 13251 0 1 SUBENT 13251001 881102 13251 1 1 BIB 13 31 13251 1 2 INSTITUTE (1USALRL) 13251 1 3 REFERENCE (J,PR,182,1251,6906) 13251 1 4 AUTHOR (D.R.NETHAWAY,B.MENDOZA,T.E.VOSS) 13251 1 5 TITLE LOW-YIELD PRODUCTS FROM FISSION OF TH232, U235, AND 13251 1 6 U238 WITH 14.8-MEV NEUTRONS 13251 1 7 FACILITY ICT NEUTRON GENERATOR 13251 1 8 INC-SOURCE (D-T) 13251 1 9 METHOD (RCHEM) 13251 1 10 DETECTOR (PROPC) GAS-FLOW BETA PROPORTIONAL COUNTERS 13251 1 11 (NAICR) NAI(TL) GAMMA DETECTORS 13251 1 12 MONITOR (39-Y-89(N,2N)39-Y-88,,SIG) FLUX MONITOR 13251 1 13 DECAY-DATA ((1.)28-NI-66,2.29D,B) 13251 1 14 ((2.)29-CU-67,2.56D,B) 13251 1 15 ((3.)30-ZN-72,1.94D,B) 13251 1 16 ((4.)39-Y-93-G,10.1HR,DG) 13251 1 17 ((5.)56-BA-140,12.80D,DG,1596.,0.962) 13251 1 18 ((6.)60-ND-147,11.04D,DG,531.,0.131) 13251 1 19 ((7.)62-SM-153,1.94D,B) 13251 1 20 ((8.)64-GD-159,0.773D,B) 13251 1 21 ((9.)65-TB-161,6.96D,B) 13251 1 22 ((10.)66-DY-166,3.40D) 13251 1 23 ((10.)67-HO-166-G,1.116D,B) 13251 1 24 ((11.)68-ER-169,9.5D,B) 13251 1 25 ((12.)68-ER-172,2.08D) 13251 1 26 ((12.)69-TM-172,2.65D,B) 13251 1 27 ERR-ANALYS DATA UNCERTAINTIES GIVEN INCLUDE UNCERATINTY IN 13251 1 28 COUNTING EFFICIENCIES AND COUNTING STATISTICS, AND 13251 1 29 STANDARD DEVIATION. NOT INCLUDED IS 6% UNCERTAINTY 13251 1 30 IN NUMBER OF FISSIONS. 13251 1 31 STATUS (RIDER) REFERENCE 69NET1 13251 1 32 HISTORY (890717C) VM 13251 1 33 ENDBIB 31 13251 1 34 COMMON 2 3 13251 1 35 EN EN-RSL 13251 1 36 MEV MEV 13251 1 37 14.8 0.3 13251 1 38 ENDCOMMON 2 3 13251 1 39 ENDSUBENT 2 13251 199999 SUBENT 13251002 881102 13251 2 1 BIB 2 2 13251 2 2 REACTION (90-TH-232(N,F)ELEM/MASS,CUM,FY) 13251 2 3 MONITOR ((MONIT2)90-TH-232(N,F),,SIG) 13251 2 4 ENDBIB 2 13251 2 5 COMMON 1 3 13251 2 6 MONIT2 13251 2 7 B 13251 2 8 0.391 13251 2 9 ENDCOMMON 1 3 13251 2 10 DATA 5 11 13251 2 11 ELEMENT MASS DATA DATA-ERR DECAY-FLAG 13251 2 12 NO-DIM NO-DIM PC/FIS PC/FIS NO-DIM 13251 2 13 28. 66. 1.31E-6 0.13E-6 1. 13251 2 14 29. 67. 2.6E-6 0.6E-6 2. 13251 2 15 30. 72. 7.0E-5 0.6E-5 3. 13251 2 16 39. 93. 0.053 0.005 4. 13251 2 17 56. 140. 0.058 0.002 5. 13251 2 18 60. 147. 0.0181 0.0013 6. 13251 2 19 62. 153. 8.6E-4 0.9E-4 7. 13251 2 20 64. 159. 4.4E-5 0.4E-5 8. 13251 2 21 65. 161. 1.06E-5 0.06E-5 9. 13251 2 22 66. 166. 2.9E-7 0.2E-7 10. 13251 2 23 68. 169. 2.3E-7 0.8E-7 11. 13251 2 24 ENDDATA 13 13251 2 25 ENDSUBENT 5 13251 299999 SUBENT 13251003 881102 13251 3 1 BIB 5 6 13251 3 2 REACTION (92-U-235(N,F)ELEM/MASS,CUM,FY) 13251 3 3 SAMPLE ENRICHED TO 93% 235U 13251 3 4 MONITOR ((MONIT2)92-U-235(N,F),,SIG) 13251 3 5 CORRECTION CORRECTED FOR 238U CONTECT IN FOILS 13251 3 6 COMMENT 166DY HAS TYPOGRAPHICAL ERROR ON EXPONENT IN TABLE II. 13251 3 7 CORRECT EXPONENT GIVEN IN TABLE IV. 13251 3 8 ENDBIB 6 13251 3 9 COMMON 1 3 13251 3 10 MONIT2 13251 3 11 B 13251 3 12 2.24 13251 3 13 ENDCOMMON 1 3 13251 3 14 DATA 5 12 13251 3 15 ELEMENT MASS DATA DATA-ERR DECAY-FLAG 13251 3 16 NO-DIM NO-DIM PC/FIS PC/FIS NO-DIM 13251 3 17 28. 66. 2.8E-6 0.3E-6 1. 13251 3 18 29. 67. 6.5E-6 0.9E-6 2. 13251 3 19 30. 72. 6.3E-5 0.3E-5 3. 13251 3 20 39. 93. 0.054 0.005 4. 13251 3 21 56. 140. 0.0425 0.0017 5. 13251 3 22 60. 147. 0.0164 0.0011 6. 13251 3 23 62. 153. 2.2E-3 0.2E-3 7. 13251 3 24 64. 159. 1.27E-4 0.13E-4 8. 13251 3 25 65. 161. 5.6E-5 0.4E-5 9. 13251 3 26 66. 166. 2.8E-6 0.2E-6 10. 13251 3 27 68. 169. 8.0E-7 0.6E-7 11. 13251 3 28 68. 172. 1.8E-7 0.2E-7 12. 13251 3 29 ENDDATA 14 13251 3 30 ENDSUBENT 5 13251 399999 SUBENT 13251006 881102 13251 6 1 BIB 3 3 13251 6 2 REACTION (92-U-238(N,F)ELEM/MASS,CUM,FY) 13251 6 3 SAMPLE ENRICHED TO 99.8% 238U 13251 6 4 MONITOR ((MONIT2)92-U-238(N,F),,SIG) 13251 6 5 ENDBIB 3 13251 6 6 COMMON 1 3 13251 6 7 MONIT2 13251 6 8 B 13251 6 9 1.24 13251 6 10 ENDCOMMON 1 3 13251 6 11 DATA 5 12 13251 6 12 ELEMENT MASS DATA DATA-ERR DECAY-FLAG 13251 6 13 NO-DIM NO-DIM PC/FIS PC/FIS NO-DIM 13251 6 14 28. 66. 8.5E-7 0.9E-7 1. 13251 6 15 29. 67. 1.4E-6 0.4E-6 2. 13251 6 16 30. 72. 3.0E-5 0.4E-5 3. 13251 6 17 39. 93. 0.044 0.004 4. 13251 6 18 56. 140. 0.0446 0.0018 5. 13251 6 19 60. 147. 0.0220 0.0015 6. 13251 6 20 62. 153. 4.2E-3 0.4E-3 7. 13251 6 21 64. 159. 2.6E-4 0.3E-4 8. 13251 6 22 65. 161. 8.9E-5 0.5E-5 9. 13251 6 23 66. 166. 6.3E-6 0.6E-6 10. 13251 6 24 68. 169. 1.29E-6 0.09E-6 11. 13251 6 25 68. 172. 2.1E-7 0.7E-7 12. 13251 6 26 ENDDATA 14 13251 6 27 ENDSUBENT 5 13251 699999 ENDENTRY 4 1325199999999 ENTRY 13253 881102 13253 0 1 SUBENT 13253001 881102 13253 1 1 BIB 11 12 13253 1 2 INSTITUTE (1USAARK) 13253 1 3 REFERENCE (J,JIN,31,591,6903) 13253 1 4 AUTHOR (S.A.RAO,M.N.RAO,P.K.KURODA) 13253 1 5 TITLE INDEPENDENT YIELDS OF 124SB, 126SB, AND 136CS IN 13253 1 6 14.8-MEV NEUTRON-INDUCED FISSION OF THORIUM AND URANIUM13253 1 7 FACILITY (CCW) 13253 1 8 METHOD (RCHEM) 13253 1 9 DETECTOR TRACERLAB CE14SL LOW BACKGORUND BETA COUNTERS 13253 1 10 MONITOR NO INFORMATION 13253 1 11 ERR-ANALYS NO INFORMATION 13253 1 12 STATUS (RIDER) REFERENCE 69RAO1 13253 1 13 HISTORY (890608C) VM 13253 1 14 ENDBIB 12 13253 1 15 COMMON 1 3 13253 1 16 EN 13253 1 17 EV 13253 1 18 14.8 E+06 13253 1 19 ENDCOMMON 1 3 13253 1 20 ENDSUBENT 1 13253 199999 SUBENT 13253002 881102 13253 2 1 BIB 3 5 13253 2 2 REACTION (90-TH-232(N,F)ELEM/MASS,IND,FY) 13253 2 3 SAMPLE THORIUM CARBONATE 13253 2 4 DECAY-DATA ((1.)51-SB-124-G,60.D) 13253 2 5 ((2.)51-SB-126-G,12.5D) 13253 2 6 ((3.)55-CS-136-G,12.9D) 13253 2 7 ENDBIB 5 13253 2 8 NOCOMMON 0 0 13253 2 9 DATA 6 3 13253 2 10 ELEMENT MASS ISOMER DATA DATA-ERR DECAY-FLAG 13253 2 11 NO-DIM NO-DIM NO-DIM PC/FIS PC/FIS NO-DIM 13253 2 12 51. 124. 0. 0.068 0.017 1. 13253 2 13 51. 126. 0. 0.017 0.004 2. 13253 2 14 55. 136. 0. 0.098 0.016 3. 13253 2 15 ENDDATA 5 13253 2 16 ENDSUBENT 6 13253 299999 SUBENT 13253003 881102 13253 3 1 BIB 2 2 13253 3 2 REACTION (92-U-238(N,F)ELEM/MASS,IND,FY) 13253 3 3 SAMPLE U(2)O(7)(NH4)2 13253 3 4 ENDBIB 2 13253 3 5 NOCOMMON 0 0 13253 3 6 DATA 5 3 13253 3 7 ELEMENT MASS ISOMER DATA DATA-ERR 13253 3 8 NO-DIM NO-DIM NO-DIM PC/FIS PC/FIS 13253 3 9 51. 124. 0. 0.024 0.005 13253 3 10 51. 126. 0. 0.010 0.004 13253 3 11 55. 136. 0. 0.049 0.008 13253 3 12 ENDDATA 5 13253 3 13 ENDSUBENT 5 13253 399999 ENDENTRY 3 1325399999999 ENTRY 13255 900705 13255 0 1 SUBENT 13255001 900117 13255 1 1 BIB 10 13 13255 1 2 INSTITUTE (1USALAS) 13255 1 3 REFERENCE (R,LA-6129,7602) DATA COMPILATION 13255 1 4 AUTHOR (G.P.FORD,A.E.NORRIS) 13255 1 5 TITLE A COMPILATION OF YIELDS FROM NEUTRON-INDUCED FISSION 13255 1 6 OF 232TH, 235U, 236U, 237NP, 238U, AND 239PU 13255 1 7 MEASURED RADIOCHEMICALLY AT LOS ALAMOS 13255 1 8 FACILITY (CCW) 13255 1 9 INC-SOURCE (D-T) 13255 1 10 METHOD (RCHEM) 13255 1 11 ERR-ANALYS NO INFORMATION 13255 1 12 STATUS (RIDER) REFERENCE 64OTH1 13255 1 13 HISTORY (890628C) VM 13255 1 14 (900117A) 13255 1 15 ENDBIB 13 13255 1 16 NOCOMMON 0 0 13255 1 17 ENDSUBENT 0 13255 199999 SUBENT 13255002 900117 13255 2 1 BIB 4 10 13255 2 2 REACTION 1(((94-PU-239(N,F)ELEM/MASS,CUM,FY)/ 13255 2 3 (94-PU-239(N,F)42-MO-99,CUM,FY))// 13255 2 4 ((92-U-235(N,F)ELEM/MASS,CUM,FY,,MXW)/ 13255 2 5 (92-U-235(N,F)42-MO-99,CUM,FY,,MXW))) 13255 2 6 2(94-PU-239(N,F)ELEM/MASS,CUM,FY) 13255 2 7 RESULT 1(RVAL) 13255 2 8 MONITOR 2((MONIT1)(94-PU-239(N,F)42-MO-99,CUM,FY)/ 13255 2 9 (92-U-235(N,F)42-MO-99,CUM,FY,,MXW)) 13255 2 10 ((MONIT2)92-U-235(N,F)ELEM/MASS,CUM,FY,,MXW) 13255 2 11 HISTORY (900117A) DATA SETS 2 AND 3 RECOMBINED 13255 2 12 ENDBIB 10 13255 2 13 COMMON 2 3 13255 2 14 EN MONIT1 2 13255 2 15 MEV NO-DIM 13255 2 16 14. 0.8805 13255 2 17 ENDCOMMON 2 3 13255 2 18 DATA 7 8 13255 2 19 MASS ELEMENT ISOMER DATA 1DATA-ERR 1DATA 213255 2 20 MONIT2 2 13255 2 21 NO-DIM NO-DIM NO-DIM NO-DIM PER-CENT PC/FIS 13255 2 22 NO-DIM 13255 2 23 89. 38. 0.497 2.4 2.12 13255 2 24 4.846 13255 2 25 111. 47. 121. 2.9 2.11 13255 2 26 0.01976 13255 2 27 115. 48. 0. 133. 1.9 13255 2 28 13255 2 29 140. 56. 0.752 1.5 4.19 13255 2 30 6.320 13255 2 31 144. 58. 0.598 4.5 2.87 13255 2 32 5.457 13255 2 33 147. 60. 0.943 2.7 1.89 13255 2 34 2.271 13255 2 35 156. 63. 19.3 1.7 0.230 13255 2 36 0.01351 13255 2 37 161. 65. 254. 5.6 0.0196 13255 2 38 8.874 -05 13255 2 39 ENDDATA 20 13255 2 40 ENDSUBENT 7 13255 299999 SUBENT 13255003 900117 13255 3 1 BIB 4 11 13255 3 2 REACTION 1(((94-PU-239(N,F)55-CS-136,IND,FY)/ 13255 3 3 (94-PU-239(N,F)42-MO-99,CUM,FY))// 13255 3 4 ((92-U-235(N,F)55-CS-136,IND,FY,,MXW)/ 13255 3 5 (92-U-235(N,F)42-MO-99,CUM,FY,,MXW))) 13255 3 6 2(94-PU-239(N,F)55-CS-136,IND,FY) 13255 3 7 RESULT 1(RVAL) 13255 3 8 MONITOR 2((MONIT1)(94-PU-239(N,F)42-MO-99,CUM,FY)/ 13255 3 9 (92-U-235(N,F)42-MO-99,CUM,FY,,MXW)) 13255 3 10 ((MONIT2)92-U-235(N,F)55-CS-136,IND,FY,,MXW) 13255 3 11 HISTORY (900117A) DATA SETS 2 AND 3 RECOMBINED. 136CS REACTION 13255 3 12 CORRECTED 13255 3 13 ENDBIB 11 13255 3 14 NOCOMMON 0 0 13255 3 15 DATA 6 1 13255 3 16 EN DATA 1DATA-ERR 1DATA 2MONIT1 2MONIT2 213255 3 17 MEV NO-DIM PER-CENT PC/FIS NO-DIM PC/FIS 13255 3 18 14. 162. 2.7 0.757 0.8805 5.308 -0313255 3 19 ENDDATA 3 13255 3 20 ENDSUBENT 6 13255 399999 SUBENT 13255004 900604 13255 4 1 BIB 4 11 13255 4 2 REACTION 1(((92-U-235(N,F)ELEM/MASS,CUM,FY)/ 13255 4 3 (92-U-235(N,F)42-MO-99,CUM,FY))// 13255 4 4 ((92-U-235(N,F)ELEM/MASS,CUM,FY,,MXW)/ 13255 4 5 (92-U-235(N,F)42-MO-99,CUM,FY,,MXW))) 13255 4 6 2(92-U-235(N,F)ELEM/MASS,CUM,FY) 13255 4 7 RESULT 1(RVAL) 13255 4 8 MONITOR 2((MONIT1)(92-U-235(N,F)42-MO-99,CUM,FY)/ 13255 4 9 (92-U-235(N,F)42-MO-99,CUM,FY,,MXW)) 13255 4 10 ((MONIT2)92-U-235(N,F)ELEM/MASS,CUM,FY,,MXW) 13255 4 11 HISTORY (900117C) 13255 4 12 (900604A) DATA FIELD CORRECTED 13255 4 13 ENDBIB 11 13255 4 14 COMMON 2 3 13255 4 15 EN MONIT1 2 13255 4 16 MEV NO-DIM 13255 4 17 14.7 0.8794 13255 4 18 ENDCOMMON 2 3 13255 4 19 DATA 7 10 13255 4 20 MASS ELEMENT ISOMER DATA 1DATA-ERR 1DATA 213255 4 21 MONIT2 2 13255 4 22 NO-DIM NO-DIM NO-DIM NO-DIM PER-CENT PC/FIS 13255 4 23 PC/FIS 13255 4 24 89. 38. 1.01 2.4 4.30 13255 4 25 4.846 13255 4 26 111. 47. 74.4 2.9 1.29 13255 4 27 0.01976 13255 4 28 115. 48. 0. 99.4 1.9 13255 4 29 13255 4 30 115. 48. 1. 102.4 4.4 13255 4 31 13255 4 32 140. 56. 0.874 1.5 4.86 13255 4 33 6.320 13255 4 34 143. 58. 0.783 0.8 4.11 13255 4 35 5.972 13255 4 36 144. 58. 0.691 4.5 3.32 13255 4 37 5.457 13255 4 38 147. 60. 0.870 2.7 1.74 13255 4 39 2.271 13255 4 40 156. 63. 4.85 1.7 0.0576 13255 4 41 0.01351 13255 4 42 161. 65. 66.2 5.6 5.11 -0313255 4 43 8.873 -05 13255 4 44 ENDDATA 24 13255 4 45 ENDSUBENT 7 13255 499999 SUBENT 13255005 900705 13255 5 1 BIB 4 13 13255 5 2 REACTION 1(((92-U-238(N,F)ELEM/MASS,CUM,FY)/ 13255 5 3 (92-U-238(N,F)42-MO-99,CUM,FY))// 13255 5 4 ((92-U-238(N,F)ELEM/MASS,CUM,FY,,MXW)/ 13255 5 5 (92-U-238(N,F)42-MO-99,CUM,FY,,MXW))) 13255 5 6 2(92-U-238(N,F)ELEM/MASS,CUM,FY) 13255 5 7 RESULT 1(RVAL) 13255 5 8 MONITOR 2((MONIT1)(92-U-238(N,F)42-MO-99,CUM,FY)/ 13255 5 9 (92-U-235(N,F)42-MO-99,CUM,FY,,MXW)) 13255 5 10 ((MONIT2)92-U-235(N,F)ELEM/MASS,CUM,FY,,MXW) 13255 5 11 VALUES FOR 136CS NOT GIVEN 13255 5 12 HISTORY (900117C) 13255 5 13 (900604A) DATA HEADINGS, DATA FIELD CORRECTED 13255 5 14 (900705A) DATA CORRECTED 13255 5 15 ENDBIB 13 13255 5 16 COMMON 2 3 13255 5 17 EN MONIT1 2 13255 5 18 MEV PC/FIS 13255 5 19 14.7 0.9300 13255 5 20 ENDCOMMON 2 3 13255 5 21 DATA 7 10 13255 5 22 MASS ELEMENT ISOMER DATA 1DATA-ERR 1DATA 213255 5 23 MONIT2 2 13255 5 24 NO-DIM NO-DIM NO-DIM NO-DIM PER-CENT PC/FIS 13255 5 25 PC/FIS 13255 5 26 89. 38. 0.664 2.4 2.99 13255 5 27 4.846 13255 5 28 111. 47. 62.0 2.9 1.14 13255 5 29 0.01976 13255 5 30 115. 48. 0. 73.7 1.9 13255 5 31 13255 5 32 115. 48. 1. 84.4 4.4 13255 5 33 13255 5 34 140. 56. 0.811 1.5 4.77 13255 5 35 6.320 13255 5 36 143. 58. 0.721 0.8 4.00 13255 5 37 5.972 13255 5 38 144. 58. 0.726 4.5 3.68 13255 5 39 5.457 13255 5 40 147. 60. 1.03 2.7 2.175 13255 5 41 2.271 13255 5 42 156. 63. 8.95 1.7 0.113 13255 5 43 0.01351 13255 5 44 161. 65. 101. 5.6 8.251-0313255 5 45 8.874 -05 13255 5 46 ENDDATA 24 13255 5 47 ENDSUBENT 7 13255 599999 ENDENTRY 5 1325599999999 ENTRY 13259 890817 13259 0 1 SUBENT 13259001 890817 13259 1 1 BIB 10 13 13259 1 2 INSTITUTE (1USAGEV) 13259 1 3 REFERENCE (P,GEAP-5505,10,6706) 13259 1 4 AUTHOR (B.F.RIDER,C.P.RUIZ,J.P.PETERSON JR,F.R.SMITH) 13259 1 5 TITLE FISSION YIELDS IN EPICADMIUM NEUTRON FISSION OF U-235, 13259 1 6 PU-239 AND U-233 13259 1 7 FACILITY (REAC) VALLECITOS BOILING WATER REACTOR 13259 1 8 INC-SPECT CD-O FILTERED SPECTRUM 13259 1 9 MONITOR (27-CO-59(N,G)27-CO-60,,RI) FLUX MONITOR 13259 1 10 ERR-ANALYS DATA UNCERTAINTIES GIVEN INCLUDE UNCERTAINTY IN: 13259 1 11 - UNCERTAINTIES IN CROSS SECTIONS 13259 1 12 - FLUX AND AXIAL FLUX DISTRIBUTION (8%) 13259 1 13 STATUS (RIDER) REFERENCE 67RID1 13259 1 14 HISTORY (890815C) VM 13259 1 15 ENDBIB 13 13259 1 16 COMMON 3 3 13259 1 17 EN-MIN MONIT MONIT-ERR 13259 1 18 EV B B 13259 1 19 0.61 72.5 2.0 13259 1 20 ENDCOMMON 3 3 13259 1 21 ENDSUBENT 3 13259 199999 SUBENT 13259002 890817 13259 2 1 BIB 2 2 13259 2 2 REACTION (92-U-233(N,F)ELEM/MASS,CUM,FY,,EPI) 13259 2 3 METHOD (RCHEM) 13259 2 4 ENDBIB 2 13259 2 5 NOCOMMON 0 0 13259 2 6 DATA 4 1 13259 2 7 ELEMENT MASS DATA DATA-ERR 13259 2 8 NO-DIM NO-DIM PC/FIS PC/FIS 13259 2 9 55. 137. 7.3 .8 13259 2 10 ENDDATA 3 13259 2 11 ENDSUBENT 4 13259 299999 SUBENT 13259003 890817 13259 3 1 BIB 2 2 13259 3 2 REACTION (92-U-233(N,F)ELEM/MASS,CUM,FY,,EPI) 13259 3 3 METHOD (ASEP) 13259 3 4 ENDBIB 2 13259 3 5 NOCOMMON 0 0 13259 3 6 DATA 4 6 13259 3 7 ELEMENT MASS DATA DATA-ERR 13259 3 8 NO-DIM NO-DIM PC/FIS PC/FIS 13259 3 9 60. 143. 5.5 .6 13259 3 10 60. 144. 4.6 .5 13259 3 11 60. 145. 3.3 .4 13259 3 12 60. 146. 2.6 .3 13259 3 13 60. 148. 1.3 .1 13259 3 14 60. 150. 0.53 .06 13259 3 15 ENDDATA 8 13259 3 16 ENDSUBENT 4 13259 399999 SUBENT 13259004 890817 13259 4 1 BIB 3 3 13259 4 2 REACTION (92-U-235(N,F)ELEM/MASS,CUM,FY,,EPI) 13259 4 3 METHOD (RCHEM) 13259 4 4 MONITOR (92-U-235(N,F)MASS,CHN,FY,,SPA) 13259 4 5 ENDBIB 3 13259 4 6 COMMON 3 3 13259 4 7 EN-NRM MASS-NRM MONIT 13259 4 8 EV NO-DIM PC/FIS 13259 4 9 0.0253 43. 5.87 13259 4 10 ENDCOMMON 3 3 13259 4 11 DATA 4 7 13259 4 12 ELEMENT MASS DATA DATA-ERR 13259 4 13 NO-DIM NO-DIM PC/FIS PC/FIS 13259 4 14 52. 132. 4.8 .5 13259 4 15 53. 131. 3.1 .3 13259 4 16 53. 134. 8.3 .8 13259 4 17 53. 135. 6.9 .7 13259 4 18 56. 140. 7.0 .7 13259 4 19 58. 141. 6.4 .6 13259 4 20 58. 143. 7.1 .7 13259 4 21 ENDDATA 9 13259 4 22 ENDSUBENT 4 13259 499999 SUBENT 13259005 890817 13259 5 1 BIB 3 3 13259 5 2 REACTION (92-U-235(N,F)ELEM/MASS,CUM,FY,,EPI) 13259 5 3 METHOD (ASEP) 13259 5 4 MONITOR HEAVY MASS YIELD CURVE SUMMED TO EQUAL 100%. 13259 5 5 ENDBIB 3 13259 5 6 NOCOMMON 0 0 13259 5 7 DATA 4 7 13259 5 8 ELEMENT MASS DATA DATA-ERR 13259 5 9 NO-DIM NO-DIM PC/FIS PC/FIS 13259 5 10 55. 137. 7.1 .8 13259 5 11 60. 143. 6.5 .7 13259 5 12 60. 144. 6.1 .7 13259 5 13 60. 145. 4.3 .5 13259 5 14 60. 146. 3.4 .4 13259 5 15 60. 148. 1.9 .2 13259 5 16 60. 150. 0.76 .09 13259 5 17 ENDDATA 9 13259 5 18 ENDSUBENT 4 13259 599999 SUBENT 13259006 890817 13259 6 1 BIB 2 2 13259 6 2 REACTION (94-PU-239(N,F)ELEM/MASS,CUM,FY,,EPI) 13259 6 3 METHOD (RCHEM) 13259 6 4 ENDBIB 2 13259 6 5 NOCOMMON 0 0 13259 6 6 DATA 4 1 13259 6 7 ELEMENT MASS DATA DATA-ERR 13259 6 8 NO-DIM NO-DIM PC/FIS PC/FIS 13259 6 9 55. 137. 6.2 .8 13259 6 10 ENDDATA 3 13259 6 11 ENDSUBENT 4 13259 699999 SUBENT 13259007 890817 13259 7 1 BIB 2 2 13259 7 2 REACTION (94-PU-239(N,F)ELEM/MASS,CUM,FY,,EPI) 13259 7 3 METHOD (ASEP) 13259 7 4 ENDBIB 2 13259 7 5 NOCOMMON 0 0 13259 7 6 DATA 4 6 13259 7 7 ELEMENT MASS DATA DATA-ERR 13259 7 8 NO-DIM NO-DIM PC/FIS PC/FIS 13259 7 9 60. 143. 3.8 .5 13259 7 10 60. 144. 3.3 .4 13259 7 11 60. 145. 2.6 .3 13259 7 12 60. 146. 2.2 .3 13259 7 13 60. 148. 1.5 .2 13259 7 14 60. 150. 0.89 .12 13259 7 15 ENDDATA 8 13259 7 16 ENDSUBENT 4 13259 799999 ENDENTRY 7 1325999999999 ENTRY 13260 890817 13260 0 1 SUBENT 13260001 890817 13260 1 1 BIB 11 11 13260 1 2 INSTITUTE (1USAGEV) 13260 1 3 REFERENCE (P,GEAP-5505,21,6706) 13260 1 4 AUTHOR (B.F.RIDER,C.P.RUIZ,J.P.PETERSON JR,F.R.SMITH) 13260 1 5 TITLE FISSION YIELDS IN FAST NEUTRON FISSION OF U-238 13260 1 6 FACILITY (REAC) VALLECITOS BOILING WATER REACTOR 13260 1 7 INC-SPECT CD-O FILTERED SPECTRUM 13260 1 8 SAMPLE UO(2) SAMPLE 13260 1 9 METHOD (ASEP) 13260 1 10 ERR-ANALYS NO INFORMATION 13260 1 11 STATUS (RIDER) REFERENCE 67RID1 13260 1 12 HISTORY (890815C) VM 13260 1 13 ENDBIB 11 13260 1 14 COMMON 1 3 13260 1 15 EN-MIN 13260 1 16 EV 13260 1 17 0.5 13260 1 18 ENDCOMMON 1 3 13260 1 19 ENDSUBENT 1 13260 199999 SUBENT 13260002 890817 13260 2 1 BIB 3 3 13260 2 2 REACTION (92-U-238(N,F)ELEM/MASS,CUM,FY,,EPI) 13260 2 3 MONITOR (92-U-238(N,F)55-CS-137,CUM,FY,,EPI) 13260 2 4 STATUS ND150 RECALCULATED BY B.F.RIDER. 13260 2 5 ENDBIB 3 13260 2 6 COMMON 2 3 13260 2 7 MONIT MONIT-ERR 13260 2 8 PC/FIS PC/FIS 13260 2 9 6.2 0.4 13260 2 10 ENDCOMMON 2 3 13260 2 11 DATA 4 6 13260 2 12 ELEMENT MASS DATA DATA-ERR 13260 2 13 NO-DIM NO-DIM PC/FIS PC/FIS 13260 2 14 60. 143. 4.3 .3 13260 2 15 60. 144. 4.3 .3 13260 2 16 60. 145. 3.5 .2 13260 2 17 60. 146. 3.2 .2 13260 2 18 60. 148. 1.93 .10 13260 2 19 60. 150. 1.16 .05 13260 2 20 ENDDATA 8 13260 2 21 ENDSUBENT 4 13260 299999 ENDENTRY 2 1326099999999 ENTRY 13268 900326 13268 0 1 SUBENT 13268001 890817 13268 1 1 BIB 11 14 13268 1 2 INSTITUTE (1CANTOR) + UNIV. OF WATERLOO 13268 1 3 REFERENCE (J,CJC,48,641,70) 13268 1 4 (J,DA/B,32,3838,7201) 13268 1 5 AUTHOR (L.H.GEVAERT,R.E.JERVIS,H.D.SHARMA) 13268 1 6 TITLE CUMULATIVE YIELDS IN THE 14 MEV NEUTRON FISSION OF 13268 1 7 232TH AND 238U IN THE SYMMETRIC REGION 13268 1 8 FACILITY (CCW) 13268 1 9 INC-SOURCE (D-T) 13268 1 10 METHOD (RCHEM) 13268 1 11 DETECTOR (GEMUC). BETA DETECTOR 13268 1 12 (NAICR,GELI). GAMMA DETECTORS 13268 1 13 ERR-ANALYS NO INFORMATION 13268 1 14 STATUS (RIDER) REFERENCE 70GEV1 13268 1 15 HISTORY (890717C) VM 13268 1 16 ENDBIB 14 13268 1 17 NOCOMMON 0 0 13268 1 18 ENDSUBENT 0 13268 199999 SUBENT 13268002 890817 13268 2 1 BIB 3 4 13268 2 2 REACTION (90-TH-232(N,F)ELEM/MASS,CUM,FY) 13268 2 3 MONITOR ((MONIT)29-CU-65(N,2N)29-CU-64,,SIG) 13268 2 4 DECAY-DATA (42-MO-99,67.HR,DG,740.,0.12,DG,780.,0.044, 13268 2 5 B-,1180.,0.83,B-,80.,0.03,B-,41.,0.14) 13268 2 6 ENDBIB 4 13268 2 7 NOCOMMON 0 0 13268 2 8 DATA 6 1 13268 2 9 EN ELEMENT MASS DATA DATA-ERR MONIT 13268 2 10 MEV NO-DIM NO-DIM PC/FIS PC/FIS B 13268 2 11 14.7 42. 99. 2.00 0.08 0.970 13268 2 12 ENDDATA 3 13268 2 13 ENDSUBENT 6 13268 299999 SUBENT 13268003 900326 13268 3 1 BIB 4 14 13268 3 2 REACTION (90-TH-232(N,F)ELEM/MASS,CUM,FY) 13268 3 3 MONITOR ((MONIT1)29-CU-65(N,2N)29-CU-64,,SIG) 13268 3 4 ((MONIT2)90-TH-232(N,F)42-MO-99,CUM,FY) 13268 3 5 DECAY-DATA ((1.)44-RU-103,39.6D,DG,497.,0.88,B-,217.,0.99) 13268 3 6 ((2.)44-RU-105,4.44HR,DG,670.,0.18,DG,726.,0.48,B-) 13268 3 7 ((3.)46-PD-109-G,13.47HR,B-,1028.,1.00) 13268 3 8 ((4.)46-PD-112,21.HR,DG,617.,0.41,B-) 13268 3 9 ((5.)47-AG-111-G,7.45D,DG,340.,0.06,B-,1040.,0.93, 13268 3 10 B-,800.,0.01,B-,690.,0.06) 13268 3 11 ((6.)47-AG-113-G,5.3HR,DG,300.,,B-) 13268 3 12 ((7.)48-CD-115-G,53.5HR,DG,336.,0.95) 13268 3 13 ((8.)50-SN-121-G,27.HR,B-,383.,1.00) 13268 3 14 ((9.)50-SN-125-G,9.7D,B-,2350.) 13268 3 15 HISTORY (900326A) BIB CORRECTION 13268 3 16 ENDBIB 14 13268 3 17 COMMON 4 3 13268 3 18 EN MONIT1 MONIT2 MONIT2-ERR 13268 3 19 MEV B PC/FIS PC/FIS 13268 3 20 14.7 0.970 2.00 0.08 13268 3 21 ENDCOMMON 4 3 13268 3 22 DATA 6 9 13268 3 23 ELEMENT MASS ISOMER DATA DATA-ERR DECAY-FLAG 13268 3 24 NO-DIM NO-DIM NO-DIM PC/FIS PC/FIS NO-DIM 13268 3 25 44. 103. 0.83 0.05 1. 13268 3 26 44. 105. 1.00 0.09 2. 13268 3 27 46. 109. 1.28 0.15 3. 13268 3 28 46. 112. 1.32 0.08 4. 13268 3 29 47. 111. 1.21 0.08 5. 13268 3 30 47. 113. 1.26 0.08 6. 13268 3 31 48. 115. 0. 1.20 0.10 7. 13268 3 32 50. 121. 0. 0.93 0.10 8. 13268 3 33 50. 125. 0. 0.52 0.04 9. 13268 3 34 ENDDATA 11 13268 3 35 ENDSUBENT 6 13268 399999 SUBENT 13268004 890817 13268 4 1 BIB 3 4 13268 4 2 REACTION (90-TH-232(N,F)MASS,CHN,FY) 13268 4 3 MONITOR ((MONIT1)29-CU-65(N,2N)29-CU-64,,SIG) 13268 4 4 ((MONIT2)90-TH-232(N,F)42-MO-99,CUM,FY) 13268 4 5 STATUS (DEP,13268003) 13268 4 6 ENDBIB 4 13268 4 7 COMMON 4 3 13268 4 8 EN MONIT1 MONIT2 MONIT2-ERR 13268 4 9 MEV B PC/FIS PC/FIS 13268 4 10 14.7 0.970 2.00 0.08 13268 4 11 ENDCOMMON 4 3 13268 4 12 DATA 3 4 13268 4 13 MASS DATA DATA-ERR 13268 4 14 NO-DIM PC/FIS PC/FIS 13268 4 15 112. 1.33 0.09 13268 4 16 115. 1.31 0.14 13268 4 17 121. 0.98 0.13 13268 4 18 125. 1.0 0.4 13268 4 19 ENDDATA 6 13268 4 20 ENDSUBENT 3 13268 499999 SUBENT 13268006 890817 13268 6 1 BIB 3 4 13268 6 2 REACTION (92-U-238(N,F)ELEM/MASS,CUM,FY) 13268 6 3 MONITOR ((MONIT)29-CU-65(N,2N)29-CU-64,,SIG) 13268 6 4 DECAY-DATA (42-MO-99,67.HR,DG,740.,0.12,DG,780.,0.044, 13268 6 5 B-,1180.,0.83,B-,80.,0.03,B-,41.,0.14) 13268 6 6 ENDBIB 4 13268 6 7 NOCOMMON 0 0 13268 6 8 DATA 6 1 13268 6 9 EN ELEMENT MASS DATA DATA-ERR MONIT 13268 6 10 MEV NO-DIM NO-DIM PC/FIS PC/FIS B 13268 6 11 14.7 42. 99. 5.60 0.14 0.970 13268 6 12 ENDDATA 3 13268 6 13 ENDSUBENT 6 13268 699999 SUBENT 13268007 900326 13268 7 1 BIB 4 14 13268 7 2 REACTION (92-U-238(N,F)ELEM/MASS,CUM,FY) 13268 7 3 MONITOR ((MONIT1)29-CU-65(N,2N)29-CU-64,,SIG) 13268 7 4 ((MONIT2)92-U-238(N,F)42-MO-99,CUM,FY) 13268 7 5 DECAY-DATA ((1.)44-RU-103,39.6D,DG,497.,0.88,B-,217.,0.99) 13268 7 6 ((2.)44-RU-105,4.44HR,DG,670.,0.18,DG,726.,0.48,B-) 13268 7 7 ((3.)46-PD-109-G,13.47HR,B-,1028.,1.00) 13268 7 8 ((4.)46-PD-112,21.HR,DG,617.,0.41,B-) 13268 7 9 ((5.)47-AG-111-G,7.45D,DG,340.,0.06,B-,1040.,0.93, 13268 7 10 B-,800.,0.01,B-,690.,0.06) 13268 7 11 ((6.)47-AG-113-G,5.3HR,DG,300.,,B-) 13268 7 12 ((7.)48-CD-115-G,53.5HR,DG,336.,0.95) 13268 7 13 ((8.)50-SN-121-G,27.HR,B-,383.,1.00) 13268 7 14 ((9.)50-SN-125-G,9.7D,B-,2350.) 13268 7 15 HISTORY (900326A) BIB CORRECTION 13268 7 16 ENDBIB 14 13268 7 17 COMMON 4 3 13268 7 18 EN MONIT1 MONIT2 MONIT2-ERR 13268 7 19 MEV B PC/FIS PC/FIS 13268 7 20 14.7 0.970 5.60 0.14 13268 7 21 ENDCOMMON 4 3 13268 7 22 DATA 6 9 13268 7 23 ELEMENT MASS ISOMER DATA DATA-ERR DECAY-FLAG 13268 7 24 NO-DIM NO-DIM NO-DIM PC/FIS PC/FIS NO-DIM 13268 7 25 44. 103. 4.44 0.15 1. 13268 7 26 44. 105. 3.00 0.10 2. 13268 7 27 46. 109. 1.54 0.15 3. 13268 7 28 46. 112. 1.24 0.05 4. 13268 7 29 47. 111. 1.10 0.05 5. 13268 7 30 47. 113. 0.88 0.05 6. 13268 7 31 48. 115. 0. 0.86 0.09 7. 13268 7 32 50. 121. 0. 1.14 0.11 8. 13268 7 33 50. 125. 0. 0.85 0.085 9. 13268 7 34 ENDDATA 11 13268 7 35 ENDSUBENT 6 13268 799999 SUBENT 13268008 890817 13268 8 1 BIB 3 3 13268 8 2 REACTION (92-U-238(N,F)MASS,CHN,FY) 13268 8 3 MONITOR (29-CU-65(N,2N)29-CU-64,,SIG) 13268 8 4 STATUS (DEP,13268007) 13268 8 5 ENDBIB 3 13268 8 6 COMMON 2 3 13268 8 7 EN MONIT 13268 8 8 MEV B 13268 8 9 14.7 0.970 13268 8 10 ENDCOMMON 2 3 13268 8 11 DATA 3 4 13268 8 12 MASS DATA DATA-ERR 13268 8 13 NO-DIM PC/FIS PC/FIS 13268 8 14 112. 1.25 0.06 13268 8 15 115. 0.93 0.12 13268 8 16 121. 1.2 0.14 13268 8 17 125. 1.5 0.4 13268 8 18 ENDDATA 6 13268 8 19 ENDSUBENT 3 13268 899999 ENDENTRY 7 1326899999999 ENTRY 13274 900406 13274 0 1 SUBENT 13274001 900403 13274 1 1 BIB 9 13 13274 1 2 INSTITUTE (1USABNW) 13274 1 3 REFERENCE (J,ACS,,(16),7404) NUCLEAR CHEM. AND TECHNOL. DIV. 13274 1 4 167TH AM. CHEM. SOC. NATIONAL MEETING, LOS ANGELES 13274 1 5 AUTHOR (N.E.BALLOU,J.H.KAYE,P.L.REEDER,R.A.ANDERL, 13274 1 6 J.J.STOFFELS) 13274 1 7 TITLE INDEPENDENT AND CUMULATIVE FISSION YIELDS FOR SEVERAL 13274 1 8 FISSION SYSTEMS 13274 1 9 METHOD (RCHEM) 13274 1 10 MONITOR NO INFORMATION 13274 1 11 ERR-ANALYS NO INFORMATION 13274 1 12 STATUS (RIDER) REFERENCE 74BAL1 13274 1 13 DATA TAKEN FROM BNWL-B-281 (1973). 13274 1 14 HISTORY (900207C) VM 13274 1 15 ENDBIB 13 13274 1 16 NOCOMMON 0 0 13274 1 17 ENDSUBENT 0 13274 199999 SUBENT 13274003 900403 13274 3 1 BIB 2 4 13274 3 2 REACTION (92-U-235(N,F)ELEM/MASS,CUM,FY) 13274 3 3 STATUS RECOMMENDED MEAN VALUE OF DATA CALCULATED RELATIVE TO 13274 3 4 4 REFERENCE NUCLIDES: 88KR=3.47%, 88RB=3.47%, 13274 3 5 138XE=3.96%, 138CS=3.96% 13274 3 6 ENDBIB 4 13274 3 7 COMMON 1 3 13274 3 8 EN 13274 3 9 MEV 13274 3 10 15. 13274 3 11 ENDCOMMON 1 3 13274 3 12 DATA 4 7 13274 3 13 ELEMENT MASS ISOMER DATA 13274 3 14 NO-DIM NO-DIM NO-DIM PC/FIS 13274 3 15 36. 85. 1. 1.84 13274 3 16 36. 87. 2.67 13274 3 17 36. 88. 3.76 13274 3 18 36. 89. 4.04 13274 3 19 54. 137. 4.45 13274 3 20 54. 138. 3.96 13274 3 21 54. 138. 3.67 13274 3 22 ENDDATA 9 13274 3 23 ENDSUBENT 4 13274 399999 SUBENT 13274004 900403 13274 4 1 BIB 2 3 13274 4 2 REACTION ((92-U-235(N,F)ELEM/MASS,IND,FY)/ 13274 4 3 (92-U-235(N,F)MASS,CHN,FY)) 13274 4 4 RESULT (FRIND) 13274 4 5 ENDBIB 3 13274 4 6 COMMON 1 3 13274 4 7 EN 13274 4 8 MEV 13274 4 9 15. 13274 4 10 ENDCOMMON 1 3 13274 4 11 DATA 3 3 13274 4 12 ELEMENT MASS DATA 13274 4 13 NO-DIM NO-DIM NO-DIM 13274 4 14 53. 138. 0.097 13274 4 15 54. 138. 0.590 13274 4 16 55. 138. 0.301 13274 4 17 ENDDATA 5 13274 4 18 ENDSUBENT 3 13274 499999 SUBENT 13274006 900403 13274 6 1 BIB 2 4 13274 6 2 REACTION (92-U-238(N,F)ELEM/MASS,CUM,FY) 13274 6 3 STATUS RECOMMENDED MEAN VALUE OF DATA CALCULATED RELATIVE TO 13274 6 4 4 REFERENCE NUCLIDES: 88KR=2.23%, 88RB=2.23%, 13274 6 5 138XE=4.22%, 138CS=4.22% 13274 6 6 ENDBIB 4 13274 6 7 COMMON 1 3 13274 6 8 EN 13274 6 9 MEV 13274 6 10 15. 13274 6 11 ENDCOMMON 1 3 13274 6 12 DATA 4 6 13274 6 13 ELEMENT MASS ISOMER DATA 13274 6 14 NO-DIM NO-DIM NO-DIM PC/FIS 13274 6 15 36. 85. 1. 0.97 13274 6 16 36. 87. 1.59 13274 6 17 36. 88. 2.20 13274 6 18 36. 89. 2.77 13274 6 19 54. 137. 4.63 13274 6 20 54. 138. 4.28 13274 6 21 ENDDATA 8 13274 6 22 ENDSUBENT 4 13274 699999 SUBENT 13274012 900403 13274 12 1 BIB 2 4 13274 12 2 REACTION (94-PU-239(N,F)ELEM/MASS,CUM,FY) 13274 12 3 STATUS RECOMMENDED MEAN VALUE OF DATA CALCULATED RELATIVE TO 13274 12 4 4 REFERENCE NUCLIDES: 88KR=1.46%, 88RB=1.46%, 13274 12 5 138XE=1.51%, 138CS=1.51% 13274 12 6 ENDBIB 4 13274 12 7 COMMON 1 3 13274 12 8 EN 13274 12 9 MEV 13274 12 10 15. 13274 12 11 ENDCOMMON 1 3 13274 12 12 DATA 4 6 13274 12 13 ELEMENT MASS ISOMER DATA 13274 12 14 NO-DIM NO-DIM NO-DIM PC/FIS 13274 12 15 36. 85. 1. 0.79 13274 12 16 36. 87. 1.10 13274 12 17 36. 88. 1.41 13274 12 18 36. 89. 1.39 13274 12 19 54. 137. 2.41 13274 12 20 54. 138. 1.54 13274 12 21 ENDDATA 8 13274 12 22 ENDSUBENT 4 13274 1299999 SUBENT 13274013 900403 13274 13 1 BIB 2 2 13274 13 2 REACTION (94-PU-239(N,F)ELEM/MASS,CUM,FY) 13274 13 3 MONITOR (94-PU-239(N,F)40-ZR-97,CUM,FY) 13274 13 4 ENDBIB 2 13274 13 5 COMMON 2 3 13274 13 6 EN MONIT 13274 13 7 MEV PC/FIS 13274 13 8 15. 4.31 13274 13 9 ENDCOMMON 2 3 13274 13 10 DATA 3 3 13274 13 11 ELEMENT MASS DATA 13274 13 12 NO-DIM NO-DIM PC/FIS 13274 13 13 53. 138. 0.09 13274 13 14 54. 138. 1.51 13274 13 15 55. 138. 3.24 13274 13 16 ENDDATA 5 13274 13 17 ENDSUBENT 3 13274 1399999 SUBENT 13274014 900403 13274 14 1 BIB 1 1 13274 14 2 REACTION (94-PU-239(N,F)MASS,CHN,FY) 13274 14 3 ENDBIB 1 13274 14 4 NOCOMMON 0 0 13274 14 5 DATA 3 1 13274 14 6 EN MASS DATA 13274 14 7 MEV NO-DIM PC/FIS 13274 14 8 15. 138. 3.41 13274 14 9 ENDDATA 3 13274 14 10 ENDSUBENT 3 13274 1499999 SUBENT 13274015 900403 13274 15 1 BIB 2 3 13274 15 2 REACTION ((94-PU-239(N,F)ELEM/MASS,IND,FY)/ 13274 15 3 (94-PU-239(N,F)MASS,CHN,FY)) 13274 15 4 RESULT (FRIND) 13274 15 5 ENDBIB 3 13274 15 6 COMMON 1 3 13274 15 7 EN 13274 15 8 MEV 13274 15 9 15. 13274 15 10 ENDCOMMON 1 3 13274 15 11 DATA 3 3 13274 15 12 ELEMENT MASS DATA 13274 15 13 NO-DIM NO-DIM NO-DIM 13274 15 14 53. 138. 0.027 13274 15 15 54. 138. 0.415 13274 15 16 55. 138. 0.507 13274 15 17 ENDDATA 5 13274 15 18 ENDSUBENT 3 13274 1599999 ENDENTRY 8 1327499999999 ENTRY 13282 890829 13282 0 1 SUBENT 13282001 890829 13282 1 1 BIB 11 14 13282 1 2 INSTITUTE (1USAORL,1USAMIS) 13282 1 3 REFERENCE (J,JIN,33,1,71) 13282 1 4 (J,DA/B,30,1578,6910) THESIS, HARBOUR, U.MISSOURI 13282 1 5 AUTHOR (R.M.HARBOUR,D.E.TROUTNER) 13282 1 6 TITLE FRACTIONAL CUMULATIVE YIELD OF 2.6 MIN 99(M)NB FROM LOW13282 1 7 ENERGY NEUTRON FISSION OF 233U, 235U, 238U AND 13282 1 8 SPONTANEOUS FISSION OF 252CF 13282 1 9 FACILITY (REAC,1USAORL) 13282 1 10 METHOD (RCHEM) 13282 1 11 DETECTOR (PROPC) PROPORTIONAL-FLOW COUNTERS 13282 1 12 DECAY-DATA (41-NB-99-M,2.6MIN,B-) 13282 1 13 ERR-ANALYS DATA UNCERTAINTIES ARE STANDARD DEVIATIONS FROM MEAN. 13282 1 14 STATUS (RIDER) REFERENCE 71HAR1 13282 1 15 HISTORY (890717C) VM 13282 1 16 ENDBIB 14 13282 1 17 NOCOMMON 0 0 13282 1 18 ENDSUBENT 0 13282 199999 SUBENT 13282004 890829 13282 4 1 BIB 4 6 13282 4 2 REACTION ((92-U-238(N,F)ELEM/MASS,CUM,FY,,EPI)/ 13282 4 3 (92-U-238(N,F)MASS,CHN,FY,,EPI)) 13282 4 4 RESULT (FRCUM) 13282 4 5 INC-SPECT EPI-CD SPECTRUM 13282 4 6 SAMPLE DEPLETED URANIUM METAL (ABOUT 5 PPM 235U), CADMIUM 13282 4 7 WRAPPED 13282 4 8 ENDBIB 6 13282 4 9 NOCOMMON 0 0 13282 4 10 DATA 6 1 13282 4 11 EN-MIN ELEMENT MASS ISOMER DATA DATA-ERR 13282 4 12 EV NO-DIM NO-DIM NO-DIM NO-DIM NO-DIM 13282 4 13 0.5 41. 99. 1. 0.30 0.03 13282 4 14 ENDDATA 3 13282 4 15 ENDSUBENT 6 13282 499999 ENDENTRY 2 1328299999999 ENTRY 13291 890829 13291 0 1 SUBENT 13291001 890829 13291 1 1 BIB 12 20 13291 1 2 INSTITUTE (1USAARK) 13291 1 3 REFERENCE (J,JIN,33,651,7103) 13291 1 4 AUTHOR (D.L.SWINDLE,R.J.WRIGHT,T.E.WARD,P.K.KURODA) 13291 1 5 TITLE DISTRIBUTION OF LOW-MASS FISSION YIELDS IN THE 14.8 MEV13291 1 6 NEUTRON INDUCED FISSION OF 238U AND 232TH 13291 1 7 FACILITY (CCW) 13291 1 8 INC-SOURCE (D-T) 13291 1 9 METHOD (RCHEM) 13291 1 10 DETECTOR (PROPC) 2PI END WINDOW METHANE FLOW PROPORTIONAL 13291 1 11 COUNTER 13291 1 12 DECAY-DATA ((1.)31-GA-73,4.9HR,B-) 13291 1 13 ((2.)32-GE-77-G,11.HR,B-) 13291 1 14 ((3.)32-GE-78,88.MIN,B-) 13291 1 15 ((4.)33-AS-77,39.HR,B-) 13291 1 16 ((5.)33-AS-78,91.MIN,B-) 13291 1 17 ((6.)33-AS-79,9.MIN,B-) 13291 1 18 ((7.)34-SE-81-G,18.MIN,B-) 13291 1 19 ERR-ANALYS NO INFORMATION 13291 1 20 STATUS (RIDER) REFERENCE 71SWI2 13291 1 21 HISTORY (890828C) VM 13291 1 22 ENDBIB 20 13291 1 23 COMMON 2 3 13291 1 24 EN EN-RSL 13291 1 25 MEV MEV 13291 1 26 14.8 0.2 13291 1 27 ENDCOMMON 2 3 13291 1 28 ENDSUBENT 2 13291 199999 SUBENT 13291002 890829 13291 2 1 BIB 3 3 13291 2 2 REACTION (90-TH-232(N,F)ELEM/MASS,CUM,FY) 13291 2 3 SAMPLE THORIUM NITRATE 13291 2 4 MONITOR (90-TH-232(N,F)42-MO-99,CUM,FY) 13291 2 5 ENDBIB 3 13291 2 6 COMMON 2 3 13291 2 7 MONIT MONIT-ERR 13291 2 8 PC/FIS PC/FIS 13291 2 9 2.0 0.1 13291 2 10 ENDCOMMON 2 3 13291 2 11 DATA 6 7 13291 2 12 ELEMENT MASS ISOMER DATA DATA-ERR DECAY-FLAG 13291 2 13 NO-DIM NO-DIM NO-DIM PC/FIS PC/FIS NO-DIM 13291 2 14 31. 73. 0.008 0.002 1. 13291 2 15 32. 77. 0.07 0.02 2. 13291 2 16 32. 78. 0.11 0.03 3. 13291 2 17 33. 77. 0.13 0.02 4. 13291 2 18 33. 78. 0.31 0.05 5. 13291 2 19 33. 79. 0.95 0.15 6. 13291 2 20 34. 81. 0. 1.21 0.20 7. 13291 2 21 ENDDATA 9 13291 2 22 ENDSUBENT 6 13291 299999 SUBENT 13291003 890829 13291 3 1 BIB 3 4 13291 3 2 REACTION (92-U-238(N,F)ELEM/MASS,CUM,FY) 13291 3 3 SAMPLE ISOTOPIC COMPOSITION OF SAMPLE: 238U (99.989%), 13291 3 4 235U (0.011%). 13291 3 5 MONITOR (92-U-238(N,F)42-MO-99,CUM,FY) 13291 3 6 ENDBIB 4 13291 3 7 COMMON 2 3 13291 3 8 MONIT MONIT-ERR 13291 3 9 PC/FIS PC/FIS 13291 3 10 5.6 0.5 13291 3 11 ENDCOMMON 2 3 13291 3 12 DATA 6 7 13291 3 13 ELEMENT MASS ISOMER DATA DATA-ERR DECAY-FLAG 13291 3 14 NO-DIM NO-DIM NO-DIM PC/FIS PC/FIS NO-DIM 13291 3 15 31. 73. 0.0053 0.001 1. 13291 3 16 32. 77. 0.030 0.005 2. 13291 3 17 32. 78. 0.040 0.005 3. 13291 3 18 33. 77. 0.030 0.005 4. 13291 3 19 33. 78. 0.041 0.010 5. 13291 3 20 33. 79. 0.18 0.03 6. 13291 3 21 34. 81. 0. 0.33 0.05 7. 13291 3 22 ENDDATA 9 13291 3 23 ENDSUBENT 6 13291 399999 ENDENTRY 3 1329199999999 ENTRY 13297 890829 13297 0 1 SUBENT 13297001 890829 13297 1 1 BIB 11 12 13297 1 2 INSTITUTE (1USAUSA) TELEDYNE ISOTOPES 13297 1 3 REFERENCE (J,NP/A,198,228,72) 13297 1 4 AUTHOR (P.ALEXANDER) 13297 1 5 TITLE INDEPENDENT YIELDS OF 133, 135XE IN THE FISSION OF 13297 1 6 235U, 238U, AND 239PU BY 14 MEV NEUTRONS 13297 1 7 FACILITY (CCW,2GERMNZ) 13297 1 8 INC-SOURCE (D-T) 13297 1 9 METHOD (RCHEM) 13297 1 10 DETECTOR 2 GERMANIUM DETECTORS 13297 1 11 ERR-ANALYS NO INFORMATION 13297 1 12 STATUS (RIDER) REFERENCE 72ALE1 13297 1 13 HISTORY (890828C) VM 13297 1 14 ENDBIB 12 13297 1 15 COMMON 1 3 13297 1 16 EN 13297 1 17 MEV 13297 1 18 14. 13297 1 19 ENDCOMMON 1 3 13297 1 20 ENDSUBENT 1 13297 199999 SUBENT 13297002 890829 13297 2 1 BIB 2 3 13297 2 2 REACTION ((92-U-235(N,F)ELEM/MASS,IND,FY)/ 13297 2 3 (92-U-235(N,F)MASS,CHN,FY)) 13297 2 4 RESULT (FRIND) 13297 2 5 ENDBIB 3 13297 2 6 NOCOMMON 0 0 13297 2 7 DATA 4 2 13297 2 8 ELEMENT MASS DATA DATA-ERR 13297 2 9 NO-DIM NO-DIM NO-DIM NO-DIM 13297 2 10 54. 133. 0.022 0.007 13297 2 11 54. 135. 0.26 0.01 13297 2 12 ENDDATA 4 13297 2 13 ENDSUBENT 4 13297 299999 SUBENT 13297003 890829 13297 3 1 BIB 2 3 13297 3 2 REACTION ((92-U-238(N,F)ELEM/MASS,IND,FY)/ 13297 3 3 (92-U-238(N,F)MASS,CHN,FY)) 13297 3 4 RESULT (FRIND) 13297 3 5 ENDBIB 3 13297 3 6 NOCOMMON 0 0 13297 3 7 DATA 4 2 13297 3 8 ELEMENT MASS DATA DATA-ERR 13297 3 9 NO-DIM NO-DIM NO-DIM NO-DIM 13297 3 10 54. 133. 0.0030 0.0013 13297 3 11 54. 135. 0.056 0.037 13297 3 12 ENDDATA 4 13297 3 13 ENDSUBENT 4 13297 399999 SUBENT 13297004 890829 13297 4 1 BIB 2 3 13297 4 2 REACTION ((94-PU-239(N,F)ELEM/MASS,IND,FY)/ 13297 4 3 (94-PU-239(N,F)MASS,CHN,FY)) 13297 4 4 RESULT (FRIND) 13297 4 5 ENDBIB 3 13297 4 6 NOCOMMON 0 0 13297 4 7 DATA 4 2 13297 4 8 ELEMENT MASS DATA DATA-ERR 13297 4 9 NO-DIM NO-DIM NO-DIM NO-DIM 13297 4 10 54. 133. 0.120 0.001 13297 4 11 54. 135. 0.46 0.03 13297 4 12 ENDDATA 4 13297 4 13 ENDSUBENT 4 13297 499999 ENDENTRY 4 1329799999999 ENTRY 13304 900326 13304 0 1 SUBENT 13304001 890907 13304 1 1 BIB 10 11 13304 1 2 INSTITUTE (1CANMCM) 13304 1 3 REFERENCE (J,CJP,50,3100,7212) 13304 1 4 AUTHOR (C.K.MATHEWS,R.H.TOMLINSON) 13304 1 5 TITLE CUMULATIVE YIELDS OF THE HEAVY FRAGMENTS IN THE FAST 13304 1 6 NEUTRON FISSION OF 238U 13304 1 7 FACILITY (REAC) MC MASTER SWIMMING POOL REACTOR 13304 1 8 SAMPLE U3O8 DEPLETED IN 235U, CADMIUM-WRAPPED 13304 1 9 METHOD (ASEP) 13304 1 10 ERR-ANALYS NO INFORMATION 13304 1 11 STATUS (RIDER) REFERENCE 72MAT1 13304 1 12 HISTORY (890712C) VM 13304 1 13 ENDBIB 11 13304 1 14 COMMON 1 3 13304 1 15 EN-MIN 13304 1 16 EV 13304 1 17 0.5 13304 1 18 ENDCOMMON 1 3 13304 1 19 ENDSUBENT 1 13304 199999 SUBENT 13304002 890907 13304 2 1 BIB 1 2 13304 2 2 REACTION ((92-U-238(N,F)ELEM/MASS,CUM,FY,,FST)/ 13304 2 3 (92-U-238(N,F)54-XE-134,CUM,FY,,FST)) 13304 2 4 ENDBIB 2 13304 2 5 NOCOMMON 0 0 13304 2 6 DATA 4 4 13304 2 7 ELEMENT MASS DATA DATA-ERR 13304 2 8 NO-DIM NO-DIM NO-DIM NO-DIM 13304 2 9 54. 131. 0.485 13304 2 10 54. 132. 0.711 13304 2 11 54. 133. 0.856 .015 13304 2 12 54. 136. 0.897 .010 13304 2 13 ENDDATA 6 13304 2 14 ENDSUBENT 4 13304 299999 SUBENT 13304003 890907 13304 3 1 BIB 1 2 13304 3 2 REACTION ((92-U-238(N,F)ELEM/MASS,CUM,FY,,FST)/ 13304 3 3 (92-U-238(N,F)55-CS-137,CUM,FY,,FST)) 13304 3 4 ENDBIB 2 13304 3 5 NOCOMMON 0 0 13304 3 6 DATA 3 2 13304 3 7 ELEMENT MASS DATA 13304 3 8 NO-DIM NO-DIM NO-DIM 13304 3 9 55. 133. 1.086 13304 3 10 55. 135. 1.128 13304 3 11 ENDDATA 4 13304 3 12 ENDSUBENT 3 13304 399999 SUBENT 13304004 890907 13304 4 1 BIB 1 2 13304 4 2 REACTION ((92-U-238(N,F)ELEM/MASS,CUM,FY,,FST)/ 13304 4 3 (92-U-238(N,F)56-BA-140,CUM,FY,,FST)) 13304 4 4 ENDBIB 2 13304 4 5 NOCOMMON 0 0 13304 4 6 DATA 4 1 13304 4 7 ELEMENT MASS DATA DATA-ERR 13304 4 8 NO-DIM NO-DIM NO-DIM NO-DIM 13304 4 9 56. 138. 0.992 .060 13304 4 10 ENDDATA 3 13304 4 11 ENDSUBENT 4 13304 499999 SUBENT 13304005 890907 13304 5 1 BIB 1 2 13304 5 2 REACTION ((92-U-238(N,F)ELEM/MASS,CUM,FY,,FST)/ 13304 5 3 (92-U-238(N,F)58-CE-142,CUM,FY,,FST)) 13304 5 4 ENDBIB 2 13304 5 5 NOCOMMON 0 0 13304 5 6 DATA 4 2 13304 5 7 ELEMENT MASS DATA DATA-ERR 13304 5 8 NO-DIM NO-DIM NO-DIM NO-DIM 13304 5 9 58. 140. 1.25 .050 13304 5 10 58. 144. 0.960 .020 13304 5 11 ENDDATA 4 13304 5 12 ENDSUBENT 4 13304 599999 SUBENT 13304006 900326 13304 6 1 BIB 2 3 13304 6 2 REACTION ((92-U-238(N,F)ELEM/MASS,CUM,FY,,FST)/ 13304 6 3 (92-U-238(N,F)60-ND-143,CUM,FY,,FST)) 13304 6 4 HISTORY (900326A) DATA POINT REMOVED 13304 6 5 ENDBIB 3 13304 6 6 NOCOMMON 0 0 13304 6 7 DATA 4 5 13304 6 8 ELEMENT MASS DATA DATA-ERR 13304 6 9 NO-DIM NO-DIM NO-DIM NO-DIM 13304 6 10 60. 144. 1.010 .019 13304 6 11 60. 145. 0.823 .014 13304 6 12 60. 146. 0.744 .012 13304 6 13 60. 148. 0.460 .009 13304 6 14 60. 150. 0.282 .006 13304 6 15 ENDDATA 7 13304 6 16 ENDSUBENT 4 13304 699999 SUBENT 13304007 890907 13304 7 1 BIB 1 2 13304 7 2 REACTION ((92-U-238(N,F)ELEM/MASS,CUM,FY,,FST)/ 13304 7 3 (92-U-238(N,F)62-SM-149,CUM,FY,,FST)) 13304 7 4 ENDBIB 2 13304 7 5 NOCOMMON 0 0 13304 7 6 DATA 4 3 13304 7 7 ELEMENT MASS DATA DATA-ERR 13304 7 8 NO-DIM NO-DIM NO-DIM NO-DIM 13304 7 9 62. 151. 0.500 .010 13304 7 10 62. 152. 0.315 .015 13304 7 11 62. 154. 0.134 .010 13304 7 12 ENDDATA 5 13304 7 13 ENDSUBENT 4 13304 799999 SUBENT 13304008 890907 13304 8 1 BIB 2 3 13304 8 2 REACTION ((92-U-238(N,F)ELEM/MASS,CUM,FY,,FST)/ 13304 8 3 (92-U-238(N,F)60-ND-145,CUM,FY,,FST)) 13304 8 4 METHOD ISOTOPE DILUTION 13304 8 5 ENDBIB 3 13304 8 6 NOCOMMON 0 0 13304 8 7 DATA 4 1 13304 8 8 ELEMENT MASS DATA DATA-ERR 13304 8 9 NO-DIM NO-DIM NO-DIM PER-CENT 13304 8 10 55. 137. 1.385 20. 13304 8 11 ENDDATA 3 13304 8 12 ENDSUBENT 4 13304 899999 SUBENT 13304009 890907 13304 9 1 BIB 3 15 13304 9 2 REACTION 1(92-U-238(N,F)MASS,CHN,FY,,FST/REL) 13304 9 3 2(92-U-238(N,F)MASS,CHN,FY,,FST) 13304 9 4 ANALYSIS OBTAINED FROM RELATIVE YIELDS 13304 9 5 XE AND CS NORMALIZED AT MASS 133 13304 9 6 BA AND CE NORMALIZED AT MASS 140 13304 9 7 CE AND ND NORMALIZED AT MASS 144 13304 9 8 ND AND SM NORMALIZED BY ADJUSTING YIELD FOR MASS 140 13304 9 9 TO MEAN OF 138 AND 154 13304 9 10 RELATIVE YIELDS ASSUMED FOR THE FOLLOWING MASSES: 13304 9 11 120-126 = 0.015, 127 = 0.032, 128 = 0.140, 13304 9 12 129 = 0.290, 130 = 0.510, 139 = 1.590, 141 = 1.440, 13304 9 13 147 = 0.710, 153 = 0.093, 155 = 0.032, 156 = 0.019, 13304 9 14 157 UP = 0.025. 13304 9 15 RELATIVE YIELDS NORMALIZED TO ADD TO 100.06%. 13304 9 16 STATUS (DEP) 13304 9 17 ENDBIB 15 13304 9 18 NOCOMMON 0 0 13304 9 19 DATA 3 20 13304 9 20 MASS DATA 1DATA 2 13304 9 21 NO-DIM NO-DIM PC/FIS 13304 9 22 131. 0.852 3.36 13304 9 23 132. 1.25 4.93 13304 9 24 133. 1.504 5.93 13304 9 25 134. 1.757 6.93 13304 9 26 135. 1.562 6.16 13304 9 27 136. 1.576 6.21 13304 9 28 137. 1.385 5.46 13304 9 29 138. 1.585 6.25 13304 9 30 140. 1.598 6.30 13304 9 31 142. 1.278 5.04 13304 9 32 143. 1.215 4.79 13304 9 33 144. 1.227 4.84 13304 9 34 145. 1.000 3.94 13304 9 35 146. 0.904 3.56 13304 9 36 148. 0.559 2.20 13304 9 37 149. 0.451 1.78 13304 9 38 150. 0.343 1.35 13304 9 39 151. 0.225 0.89 13304 9 40 152. 0.142 0.56 13304 9 41 154. 0.060 0.24 13304 9 42 ENDDATA 22 13304 9 43 ENDSUBENT 3 13304 999999 ENDENTRY 9 1330499999999 ENTRY 13305 890907 13305 0 1 SUBENT 13305001 890907 13305 1 1 BIB 12 12 13305 1 2 INSTITUTE (1USAARK) 13305 1 3 REFERENCE (J,PR/C,5,171,7201) 13305 1 4 AUTHOR (S.A.RAO) 13305 1 5 TITLE CHARGE DISTRIBUTION IN THE FISSION OF TH232 13305 1 6 FACILITY (CCW) 13305 1 7 SAMPLE REAGENT GRADE TH(NO3)4 13305 1 8 METHOD (RCHEM) 13305 1 9 DETECTOR (GELI) 13305 1 10 MONITOR (90-TH-232(N,F)42-MO-99,CUM,FY) 13305 1 11 ERR-ANALYS NO INFORMATION 13305 1 12 STATUS (RIDER) REFERENCE 72RAO1 13305 1 13 HISTORY (890830C) VM 13305 1 14 ENDBIB 12 13305 1 15 COMMON 1 3 13305 1 16 EN 13305 1 17 MEV 13305 1 18 14.8 13305 1 19 ENDCOMMON 1 3 13305 1 20 ENDSUBENT 1 13305 199999 SUBENT 13305002 890907 13305 2 1 BIB 2 10 13305 2 2 REACTION (90-TH-232(N,F)ELEM/MASS,IND,FY) 13305 2 3 DECAY-DATA ((1.)41-NB-95-M,87.HR) 13305 2 4 ((1.)41-NB-95-G,35.1D) 13305 2 5 ((2.)41-NB-96,23.HR) 13305 2 6 ((3.)43-TC-99-M,6.0HR) 13305 2 7 ((4.)45-RH-106-M,2.2HR) 13305 2 8 ((5.)47-AG-112,3.2HR) 13305 2 9 ((6.)49-IN-115-M,4.5HR) 13305 2 10 ((7.)55-CS-134-M,2.9HR) 13305 2 11 ((8.)55-CS-135-M,53.MIN) 13305 2 12 ENDBIB 10 13305 2 13 NOCOMMON 0 0 13305 2 14 DATA 6 8 13305 2 15 ELEMENT MASS ISOMER DATA DATA-ERR DECAY-FLAG 13305 2 16 NO-DIM NO-DIM NO-DIM PC/FIS PC/FIS NO-DIM 13305 2 17 41. 95. 0.19 0.04 1. 13305 2 18 41. 96. 8.7E-2 2.0E-2 2. 13305 2 19 43. 99. 1. 3.6E-3 0.7E-3 3. 13305 2 20 45. 106. 1. 7.9E-3 1.4E-3 4. 13305 2 21 47. 112. 1.4E-2 0.3E-2 5. 13305 2 22 49. 115. 1. 1.9E-2 0.4E-2 6. 13305 2 23 55. 134. 1. 4.3E-2 0.4E-2 7. 13305 2 24 55. 135. 1. 1.2E-1 0.3E-1 8. 13305 2 25 ENDDATA 10 13305 2 26 ENDSUBENT 6 13305 299999 SUBENT 13305003 890907 13305 3 1 BIB 2 6 13305 3 2 REACTION (90-TH-232(N,F)ELEM/MASS,CUM,FY) 13305 3 3 DECAY-DATA ((1.)47-AG-111,7.5D) 13305 3 4 ((2.)47-AG-112,3.2HR) 13305 3 5 ((3.)47-AG-113,5.3HR) 13305 3 6 ((4.)47-AG-115,21.MIN) 13305 3 7 ((5.)48-CD-115-G,2.3D) 13305 3 8 ENDBIB 6 13305 3 9 NOCOMMON 0 0 13305 3 10 DATA 6 5 13305 3 11 ELEMENT MASS ISOMER DATA DATA-ERR DECAY-FLAG 13305 3 12 NO-DIM NO-DIM NO-DIM PC/FIS PC/FIS NO-DIM 13305 3 13 47. 111. 1.02 0.10 1. 13305 3 14 47. 112. 1.18 0.07 2. 13305 3 15 47. 113. 1.09 0.05 3. 13305 3 16 47. 115. 0.94 0.06 4. 13305 3 17 48. 115. 0. 1.12 0.08 5. 13305 3 18 ENDDATA 7 13305 3 19 ENDSUBENT 6 13305 399999 ENDENTRY 3 1330599999999 ENTRY 13309 890907 13309 0 1 SUBENT 13309001 890907 13309 1 1 BIB 14 15 13309 1 2 INSTITUTE (1USAARK) 13309 1 3 REFERENCE (J,JIN,35,3075,7309) 13309 1 4 AUTHOR (L.R.BATTLES,D.M.CHITTENDEN) 13309 1 5 TITLE YIELDS OF LOW MASS PRODUCTS IN THE FISSION OF 232TH BY 13309 1 6 14.8 MEV NEUTRONS 13309 1 7 FACILITY (CCW) 13309 1 8 INC-SOURCE (D-T) 13309 1 9 SAMPLE REAGENT GRADE TH(NO3)4.4H2O 13309 1 10 METHOD (RCHEM) 13309 1 11 DETECTOR (GEMUC) 2PI END-WINDOW GAS-FLOW GEIGER COUNTER 13309 1 12 MONITOR (90-TH-232(N,F)42-MO-99,CUM,FY) 13309 1 13 CORRECTION CORRECTED FOR SELF-SCATTERING AND SELF-ABSORPTION 13309 1 14 ERR-ANALYS NO INFORMATION ON SOURCE OF DATA UNCERTAINTIES GIVEN 13309 1 15 STATUS (RIDER) REFERENCE 73BAT1 13309 1 16 HISTORY (890627C) VM 13309 1 17 ENDBIB 15 13309 1 18 COMMON 4 3 13309 1 19 EN EN-RSL MONIT MONIT-ERR 13309 1 20 MEV MEV PC/FIS PC/FIS 13309 1 21 14.8 0.2 2.0 0.1 13309 1 22 ENDCOMMON 4 3 13309 1 23 ENDSUBENT 4 13309 199999 SUBENT 13309002 890907 13309 2 1 BIB 1 1 13309 2 2 REACTION (90-TH-232(N,F)ELEM/MASS,CUM,FY) 13309 2 3 ENDBIB 1 13309 2 4 NOCOMMON 0 0 13309 2 5 DATA 4 7 13309 2 6 ELEMENT MASS DATA DATA-ERR 13309 2 7 NO-DIM NO-DIM PC/FIS PC/FIS 13309 2 8 28. 66. 1.0E-4 0.1E-4 13309 2 9 29. 67. 1.6E-4 0.2E-4 13309 2 10 30. 72. 1.1E-3 0.2E-3 13309 2 11 31. 72. 5.6E-3 0.8E-3 13309 2 12 31. 73. 0.016 0.002 13309 2 13 32. 77. 0.10 0.02 13309 2 14 33. 77. 0.13 0.02 13309 2 15 ENDDATA 9 13309 2 16 ENDSUBENT 4 13309 299999 ENDENTRY 2 1330999999999 ENTRY 13312 890907 13312 0 1 SUBENT 13312001 890907 13312 1 1 BIB 10 14 13312 1 2 INSTITUTE (1USAIIT) 13312 1 3 REFERENCE (J,BAP,18,768(AB8),7306) 13312 1 4 AUTHOR (J.W.MANDLER,J.H.REED,R.B.MOLER) 13312 1 5 TITLE RELATIVE YIELDS FROM FISSION OF U235 AND U238 WITH 1-, 13312 1 6 2-, 4-, 6-, 9-, AND 14-MEV NEUTRONS 13312 1 7 FACILITY ACCELERATORS: 8-MEV TANDEM DYNAMITRON, 13312 1 8 4-MEV DYNAMITRON 13312 1 9 2-MEV VAN-DE-GRAAFF 13312 1 10 INC-SOURCE SOURCES: P-LI, D-D, D-T 13312 1 11 METHOD (RCHEM) 13312 1 12 ERR-ANALYS NO INFORMATION 13312 1 13 STATUS (RIDER) REFERENCE 73MAN1 13312 1 14 DATA TAKEN FROM CUNINGHAME, AERE-R-7548 (1973) 13312 1 15 HISTORY (890713C) VM 13312 1 16 ENDBIB 14 13312 1 17 NOCOMMON 0 0 13312 1 18 ENDSUBENT 0 13312 199999 SUBENT 13312002 890907 13312 2 1 BIB 1 2 13312 2 2 REACTION ((92-U-235(N,F)MASS,CHN,FY,,FIS)// 13312 2 3 (92-U-235(N,F)MASS,CHN,FY,,FIS)) 13312 2 4 ENDBIB 2 13312 2 5 COMMON 1 3 13312 2 6 MASS-DN 13312 2 7 NO-DIM 13312 2 8 140. 13312 2 9 ENDCOMMON 1 3 13312 2 10 DATA 4 20 13312 2 11 EN MASS-NM DATA DATA-ERR 13312 2 12 MEV NO-DIM NO-DIM NO-DIM 13312 2 13 15. 91. 1.06 0.09 13312 2 14 15. 92. 1.08 0.11 13312 2 15 15. 93. 1.09 0.11 13312 2 16 15. 95. 1.09 0.09 13312 2 17 15. 97. 1.22 0.11 13312 2 18 15. 99. 1.12 0.10 13312 2 19 15. 103. 0.76 0.06 13312 2 20 15. 105. 0.37 0.04 13312 2 21 15. 112. 0.24 0.02 13312 2 22 15. 127. 0.50 0.02 13312 2 23 15. 129. 0.71 0.05 13312 2 24 15. 131. 0.93 0.09 13312 2 25 15. 132. 1.09 0.09 13312 2 26 15. 133. 1.18 0.13 13312 2 27 15. 135. 1.24 0.08 13312 2 28 15. 137. 1.10 0.07 13312 2 29 15. 143. 0.85 0.11 13312 2 30 15. 144. 0.72 0.09 13312 2 31 15. 147. 0.44 0.03 13312 2 32 15. 151. 0.045 0.010 13312 2 33 ENDDATA 22 13312 2 34 ENDSUBENT 4 13312 299999 SUBENT 13312003 890907 13312 3 1 BIB 1 2 13312 3 2 REACTION ((92-U-238(N,F)MASS,CHN,FY,,FIS)// 13312 3 3 (92-U-238(N,F)MASS,CHN,FY,,FIS)) 13312 3 4 ENDBIB 2 13312 3 5 COMMON 1 3 13312 3 6 MASS-DN 13312 3 7 NO-DIM 13312 3 8 140. 13312 3 9 ENDCOMMON 1 3 13312 3 10 DATA 4 20 13312 3 11 EN MASS-NM DATA DATA-ERR 13312 3 12 MEV NO-DIM NO-DIM NO-DIM 13312 3 13 15. 91. 0.78 0.04 13312 3 14 15. 92. 0.87 0.07 13312 3 15 15. 93. 0.96 0.07 13312 3 16 15. 95. 1.13 0.03 13312 3 17 15. 97. 1.24 0.07 13312 3 18 15. 99. 1.23 0.04 13312 3 19 15. 103. 0.97 0.04 13312 3 20 15. 105. 0.74 0.03 13312 3 21 15. 112. 0.150 0.006 13312 3 22 15. 127. 0.037 0.02 13312 3 23 15. 129. 0.64 0.04 13312 3 24 15. 131. 1.05 0.05 13312 3 25 15. 132. 1.02 0.03 13312 3 26 15. 133. 1.44 0.10 13312 3 27 15. 135. 1.18 0.04 13312 3 28 15. 137. 1.16 0.08 13312 3 29 15. 143. 0.78 0.04 13312 3 30 15. 144. 0.72 0.07 13312 3 31 15. 147. 0.43 0.01 13312 3 32 15. 151. 0.187 0.007 13312 3 33 ENDDATA 22 13312 3 34 ENDSUBENT 4 13312 399999 ENDENTRY 3 1331299999999 ENTRY 13313 890907 13313 0 1 SUBENT 13313001 890907 13313 1 1 BIB 11 12 13313 1 2 INSTITUTE (1USAARK) 13313 1 3 REFERENCE (J,JIN,35,1443,7305) 13313 1 4 AUTHOR (S.A.RAO,P.K.KURODA) 13313 1 5 TITLE CHARGE DISTRIBUTION IN NEUTRON-INDUCED FISSION OF 13313 1 6 THORIUM 13313 1 7 FACILITY (CCW) 13313 1 8 SAMPLE TH(NO3)4.4H2O 13313 1 9 METHOD (RCHEM) 13313 1 10 DETECTOR (GELI) 13313 1 11 ERR-ANALYS NO INFORMATION 13313 1 12 STATUS (RIDER) REFERENCE 73RAO1 13313 1 13 HISTORY (890626C) VM 13313 1 14 ENDBIB 12 13313 1 15 COMMON 1 3 13313 1 16 EN 13313 1 17 MEV 13313 1 18 14.8 13313 1 19 ENDCOMMON 1 3 13313 1 20 ENDSUBENT 1 13313 199999 SUBENT 13313002 890907 13313 2 1 BIB 3 7 13313 2 2 REACTION (90-TH-232(N,F)ELEM/MASS,IND,FY) 13313 2 3 MONITOR (90-TH-232(N,F)42-MO-99,IND,FY) 13313 2 4 DECAY-DATA ((1.)49-IN-117-M,1.94HR) 13313 2 5 ((1.)49-IN-117-G,45.MIN) 13313 2 6 ((2.)53-I-130-M,9.2MIN) 13313 2 7 ((2.)53-I-130-G,12.5HR) 13313 2 8 ((3.)53-I-132,2.29HR) 13313 2 9 ENDBIB 7 13313 2 10 NOCOMMON 0 0 13313 2 11 DATA 6 3 13313 2 12 ELEMENT MASS ISOMER DATA DATA-ERR DECAY-FLAG 13313 2 13 NO-DIM NO-DIM NO-DIM PC/FIS PC/FIS NO-DIM 13313 2 14 49. 117. 0.016 0.004 1. 13313 2 15 53. 130. 0.022 0.005 2. 13313 2 16 53. 132. 0. 0.11 0.02 3. 13313 2 17 ENDDATA 5 13313 2 18 ENDSUBENT 6 13313 299999 SUBENT 13313003 890907 13313 3 1 BIB 3 5 13313 3 2 REACTION (90-TH-232(N,F)ELEM/MASS,IND,FY) 13313 3 3 MONITOR (90-TH-232(N,F)53-I-135,IND,FY) 13313 3 4 DECAY-DATA ((1.)53-I-133,20.8HR) 13313 3 5 ((2.)53-I-134-M,3.8MIN) 13313 3 6 ((2.)53-I-134-G,53.MIN) 13313 3 7 ENDBIB 5 13313 3 8 NOCOMMON 0 0 13313 3 9 DATA 5 2 13313 3 10 ELEMENT MASS DATA DATA-ERR DECAY-FLAG 13313 3 11 NO-DIM NO-DIM PC/FIS PC/FIS NO-DIM 13313 3 12 53. 133. 0.44 0.10 1. 13313 3 13 53. 134. 0.64 0.15 2. 13313 3 14 ENDDATA 4 13313 3 15 ENDSUBENT 5 13313 399999 SUBENT 13313004 890907 13313 4 1 BIB 3 5 13313 4 2 REACTION ((90-TH-232(N,F)ELEM/MASS,IND,FY)/ 13313 4 3 (90-TH-232(N,F)MASS,CHN,FY)) 13313 4 4 RESULT (FRIND) 13313 4 5 STATUS (DEP,13313002) 13313 4 6 (DEP,13313003) 13313 4 7 ENDBIB 5 13313 4 8 NOCOMMON 0 0 13313 4 9 DATA 5 5 13313 4 10 ELEMENT MASS ISOMER DATA DATA-ERR 13313 4 11 NO-DIM NO-DIM NO-DIM NO-DIM NO-DIM 13313 4 12 49. 117. 1.4E-2 0.4E-2 13313 4 13 53. 130. 1.5E-2 0.4E-2 13313 4 14 53. 132. 0. 3.6E-2 0.7E-2 13313 4 15 53. 133. 1.2E-1 0.3E-1 13313 4 16 53. 134. 9.5E-2 2.5E-2 13313 4 17 ENDDATA 7 13313 4 18 ENDSUBENT 5 13313 499999 ENDENTRY 4 1331399999999 ENTRY 13326 891023 13326 0 1 SUBENT 13326001 891023 13326 1 1 BIB 7 8 13326 1 2 INSTITUTE (1USALAS) 13326 1 3 REFERENCE (W,KNOBELOCH,72) UNPUBLISHED RESULTS. CITED IN 13326 1 4 WOLFSBERG, LA-5553-MS (1974) AS REF 72KNO1. 13326 1 5 AUTHOR (G.W.KNOBELOCH) 13326 1 6 METHOD (RCHEM) 13326 1 7 ERR-ANALYS NO INFORMATION 13326 1 8 STATUS (RIDER) REFERENCE 72KNO1 13326 1 9 HISTORY (890907C) VM 13326 1 10 ENDBIB 8 13326 1 11 NOCOMMON 0 0 13326 1 12 ENDSUBENT 0 13326 199999 SUBENT 13326004 891023 13326 4 1 BIB 2 3 13326 4 2 REACTION ((92-U-238(N,F)ELEM/MASS,IND,FY)/ 13326 4 3 (92-U-238(N,F)MASS,CHN,FY)) 13326 4 4 RESULT (FRIND) 13326 4 5 ENDBIB 3 13326 4 6 COMMON 1 3 13326 4 7 EN 13326 4 8 MEV 13326 4 9 14. 13326 4 10 ENDCOMMON 1 3 13326 4 11 DATA 4 1 13326 4 12 ELEMENT MASS DATA DATA-ERR 13326 4 13 NO-DIM NO-DIM NO-DIM NO-DIM 13326 4 14 55. 136. 5.00E-3 5.0E-4 13326 4 15 ENDDATA 3 13326 4 16 ENDSUBENT 4 13326 499999 SUBENT 13326006 891023 13326 6 1 BIB 2 3 13326 6 2 REACTION ((94-PU-239(N,F)ELEM/MASS,IND,FY)/ 13326 6 3 (94-PU-239(N,F)MASS,CHN,FY)) 13326 6 4 RESULT (FRIND) 13326 6 5 ENDBIB 3 13326 6 6 COMMON 1 3 13326 6 7 EN 13326 6 8 MEV 13326 6 9 14. 13326 6 10 ENDCOMMON 1 3 13326 6 11 DATA 4 1 13326 6 12 ELEMENT MASS DATA DATA-ERR 13326 6 13 NO-DIM NO-DIM NO-DIM NO-DIM 13326 6 14 55. 136. 0.158 0.016 13326 6 15 ENDDATA 3 13326 6 16 ENDSUBENT 4 13326 699999 ENDENTRY 3 1332699999999 ENTRY 13332 891023 13332 0 1 SUBENT 13332001 891023 13332 1 1 BIB 13 15 13332 1 2 INSTITUTE (1USAARK) 13332 1 3 REFERENCE (J,JIN,37,419,75) 13332 1 4 (J,DA/B,36,2799,7512) 13332 1 5 AUTHOR (D.E.ADAMS,W.D.JAMES,J.N.BECK,P.K.KURODA) 13332 1 6 TITLE DISTRIBUTION OF FISSION YIELDS IN THE 14.8 MEV 13332 1 7 NEUTRON-INDUCED FISSION OF 238U 13332 1 8 FACILITY (CCW) 13332 1 9 INC-SOURCE (D-T) 13332 1 10 SAMPLE CD-WRAPPED URANIUM NITRATE, 99.989% 238U, 0.011% 235U 13332 1 11 METHOD (RCHEM) 13332 1 12 DETECTOR (PROPC) 2 PI END-WINDOW BETA COUNTERS 13332 1 13 MONITOR (92-U-238(N,F)42-MO-99,CUM,FY) 13332 1 14 ERR-ANALYS NO INFORMATION 13332 1 15 STATUS (RIDER) REFERENCE 75ADA1 13332 1 16 HISTORY (891020C) VM 13332 1 17 ENDBIB 15 13332 1 18 COMMON 4 3 13332 1 19 EN EN-RSL MONIT MONIT-ERR 13332 1 20 MEV MEV PC/FIS PC/FIS 13332 1 21 14.8 0.2 5.6 0.5 13332 1 22 ENDCOMMON 4 3 13332 1 23 ENDSUBENT 4 13332 199999 SUBENT 13332002 891023 13332 2 1 BIB 1 1 13332 2 2 REACTION (92-U-238(N,F)ELEM/MASS,CUM,FY) 13332 2 3 ENDBIB 1 13332 2 4 NOCOMMON 0 0 13332 2 5 DATA 6 45 13332 2 6 MASS ELEMENT ELEMENT ISOMER DATA DATA-ERR 13332 2 7 NO-DIM NO-DIM NO-DIM NO-DIM PC/FIS PC/FIS 13332 2 8 83. 35. 0.70 0.06 13332 2 9 84. 35. 1.09 0.08 13332 2 10 89. 38. 3.19 0.20 13332 2 11 91. 38. 4.14 0.37 13332 2 12 92. 38. 3.93 0.42 13332 2 13 93. 39. 4.63 0.24 13332 2 14 94. 39. 4.84 0.60 13332 2 15 95. 40. 5.21 0.27 13332 2 16 97. 40. 5.55 0.58 13332 2 17 101. 42. 5.84 0.45 13332 2 18 102. 42. 4.61 0.51 13332 2 19 103. 44. 5.04 0.28 13332 2 20 105. 45. 2.90 0.38 13332 2 21 109. 46. 1.25 0.20 13332 2 22 111. 46. 47. 0.97 0.18 13332 2 23 112. 46. 0.93 0.16 13332 2 24 113. 47. 1.09 0.18 13332 2 25 115. 48. 0. 0.87 0.15 13332 2 26 117. 48. 0.80 0.16 13332 2 27 118. 48. 0.86 0.16 13332 2 28 121. 50. 0.86 0.14 13332 2 29 123. 50. 0. 1.09 0.20 13332 2 30 125. 50. 0.96 0.15 13332 2 31 127. 51. 1.53 0.15 13332 2 32 128. 50. 1.46 0.19 13332 2 33 129. 51. 52. 1.38 0.26 13332 2 34 131. 52. 0. 3.83 0.51 13332 2 35 132. 52. 53. 4.11 0.31 13332 2 36 133. 53. 5.68 0.51 13332 2 37 134. 53. 6.35 0.30 13332 2 38 135. 53. 5.39 0.44 13332 2 39 138. 55. 4.93 0.46 13332 2 40 139. 56. 5.44 0.41 13332 2 41 140. 56. 4.54 0.40 13332 2 42 141. 57. 58. 4.58 0.31 13332 2 43 142. 57. 3.81 0.28 13332 2 44 143. 58. 4.25 0.10 13332 2 45 144. 58. 3.88 0.30 13332 2 46 145. 59. 2.84 0.08 13332 2 47 147. 60. 1.97 0.09 13332 2 48 149. 61. 1.65 0.19 13332 2 49 151. 61. 0.64 0.10 13332 2 50 153. 62. 0.36 0.07 13332 2 51 156. 63. 0.11 0.02 13332 2 52 157. 63. 0.08 0.02 13332 2 53 ENDDATA 47 13332 2 54 ENDSUBENT 6 13332 299999 ENDENTRY 2 1333299999999 ENTRY 13345 900604 13345 0 1 SUBENT 13345001 891128 13345 1 1 BIB 9 9 13345 1 2 INSTITUTE (1USALRL) 13345 1 3 REFERENCE (J,PR/C,6,1821,7211) 13345 1 4 AUTHOR (D.R.NETHAWAY,B.MENDOZA) 13345 1 5 TITLE FISSION OF 234U AND 236U WITH 14.8-MEV NEUTRONS 13345 1 6 FACILITY (ICTR) 13345 1 7 INC-SOURCE (D-T) 13345 1 8 METHOD (RCHEM) 13345 1 9 STATUS (RIDER) REFERENCE 72NET1 13345 1 10 HISTORY (891026C) VM 13345 1 11 ENDBIB 9 13345 1 12 COMMON 1 3 13345 1 13 EN 13345 1 14 MEV 13345 1 15 14.8 13345 1 16 ENDCOMMON 1 3 13345 1 17 ENDSUBENT 1 13345 199999 SUBENT 13345002 891128 13345 2 1 BIB 7 20 13345 2 2 REACTION (92-U-234(N,F)MASS,CHN,FY) 13345 2 3 SAMPLE U(3)O(8) SAMPLE. ISOTOPIC COMPOSITION: 234U (99.33%), 13345 2 4 233U (<.0005%), 235U (0.36%), 236U (0.11%), 13345 2 5 238U (0.20%) 13345 2 6 DETECTOR (PROPC) GAS-FLOW BETA PROPORTIONAL COUNTERS 13345 2 7 MONITOR (92-U-234(N,F)60-ND-147,CUM,FY) 13345 2 8 DECAY-DATA ((1.)28-NI-66,2.29D,B) 13345 2 9 ((2.)29-CU-67,2.56D,B) 13345 2 10 ((3.)30-ZN-72,1.942D,B) 13345 2 11 ((4.)39-Y-93,0.427D,B) 13345 2 12 ((5.)58-CE-141,32.4D,B) 13345 2 13 ((6.)58-CE-144,284.0D,B) 13345 2 14 ((7.)62-SM-153,1.928D,B) 13345 2 15 ((8.)64-GD-159,0.773D,B) 13345 2 16 ((9.)65-TB-161,6.96D,B) 13345 2 17 CORRECTION CORRECTED FOR INDEPENDENT YIELD FORMATION BY LATER 13345 2 18 MEMBERS OF CHAIN 13345 2 19 ERR-ANALYS DATA UNCERTAINTIES GIVEN ARE STANDARD DEVIATIONS AND DO13345 2 20 NOT INCLUDE 5-10% UNCERTAINTY IN THE NORMALIZATION OF 13345 2 21 THE MASS YIELD CURVE 13345 2 22 ENDBIB 20 13345 2 23 COMMON 1 3 13345 2 24 MONIT 13345 2 25 PC/FIS 13345 2 26 0.0132 13345 2 27 ENDCOMMON 1 3 13345 2 28 DATA 4 9 13345 2 29 MASS DATA DATA-ERR DECAY-FLAG 13345 2 30 NO-DIM PC/FIS PC/FIS NO-DIM 13345 2 31 66. 4.6 -06 0.5 -06 1. 13345 2 32 67. 1.09 -05 0.11 -05 2. 13345 2 33 72. 1.06 -04 0.06 -04 3. 13345 2 34 93. 0.052 0.005 4. 13345 2 35 141. 0.038 0.003 5. 13345 2 36 144. 0.0277 0.0020 6. 13345 2 37 153. 1.88 -03 0.15 -03 7. 13345 2 38 159. 1.20 -04 0.12 -04 8. 13345 2 39 161. 4.7 -05 0.5 -05 9. 13345 2 40 ENDDATA 11 13345 2 41 ENDSUBENT 4 13345 299999 SUBENT 13345003 900604 13345 3 1 BIB 8 23 13345 3 2 REACTION (92-U-234(N,F)MASS,CHN,FY) 13345 3 3 SAMPLE U(3)O(8) SAMPLE. ISOTOPIC COMPOSITION: 234U (99.33%), 13345 3 4 233U (<.0005%), 235U (0.36%), 236U (0.11%), 13345 3 5 DETECTOR (NAICR) 13345 3 6 MONITOR (92-U-234(N,F)60-ND-147,CUM,FY) 13345 3 7 DECAY-DATA ((1.)40-ZR-95,65.D,DG,765.,0.99) 13345 3 8 ((2.)40-ZR-97,0.701D,DG,743.,0.94) 13345 3 9 ((3.)42-MO-99,2.752D,DG,739.,0.124) 13345 3 10 ((4.)45-RH-105,1.476D,DG,319.,0.19) 13345 3 11 ((5.)47-AG-111,7.45D,B,,,DG) 13345 3 12 ((6.)46-PD-112,0.875D,DG,617.,0.435) 13345 3 13 ((7.)52-TE-132,3.24D,DG,668.,0.98) 13345 3 14 ((8.)55-CS-137,10960.0D,DG,662.,0.85) 13345 3 15 ((9.)56-BA-140,12.80D,DG,1596.,0.96) 13345 3 16 ((10.)58-CE-143,1.379D,DG,293.,0.47) 13345 3 17 ((11.)60-ND-147,11.04D,DG,531.,0.132) 13345 3 18 ((12.)63-EU-156,15.19D,DG,812.,0.108) 13345 3 19 CORRECTION CORRECTED FOR INDEPENDENT YIELD FORMATION BY LATER 13345 3 20 MEMBERS OF CHAIN 13345 3 21 ERR-ANALYS DATA UNCERTAINTIES GIVEN ARE STANDARD DEVIATIONS AND DO13345 3 22 NOT INCLUDE 5-10% UNCERTAINTY IN THE NORMALIZATION OF 13345 3 23 THE MASS YIELD CURVE 13345 3 24 HISTORY (900604A) BIB CORRECTIONS 13345 3 25 ENDBIB 23 13345 3 26 COMMON 1 3 13345 3 27 MONIT 13345 3 28 PC/FIS 13345 3 29 0.0132 13345 3 30 ENDCOMMON 1 3 13345 3 31 DATA 4 12 13345 3 32 MASS DATA DATA-ERR DECAY-FLAG 13345 3 33 NO-DIM PC/FIS PC/FIS NO-DIM 13345 3 34 95. 0.052 0.002 1. 13345 3 35 97. 0.0506 0.003 2. 13345 3 36 99. 0.044 0.004 3. 13345 3 37 105. 0.0221 0.0018 4. 13345 3 38 111. 0.0136 0.0005 5. 13345 3 39 112. 0.0152 0.0010 6. 13345 3 40 132. 0.043 0.004 7. 13345 3 41 137. 0.0512 0.0023 8. 13345 3 42 140. 0.0395 0.0016 9. 13345 3 43 143. 0.0339 0.0017 10. 13345 3 44 147. 0.0132 0.0009 11. 13345 3 45 156. 4.86 -04 0.22 -0412. 13345 3 46 ENDDATA 14 13345 3 47 ENDSUBENT 4 13345 399999 SUBENT 13345004 891128 13345 4 1 BIB 6 12 13345 4 2 REACTION (92-U-234(N,F)MASS,CHN,FY) 13345 4 3 THE MEASURED 115M/115G RATIO = 0.067 13345 4 4 SAMPLE U(3)O(8) SAMPLE. ISOTOPIC COMPOSITION: 234U (99.33%), 13345 4 5 233U (<.0005%), 235U (0.36%), 236U (0.11%), 13345 4 6 238U (0.20%) 13345 4 7 DETECTOR (GELI) 13345 4 8 MONITOR (92-U-234(N,F)60-ND-147,CUM,FY) 13345 4 9 DECAY-DATA (48-CD-115-G,2.208D,DG,336.,0.50) 13345 4 10 (48-CD-115-M,43.0D,B) 13345 4 11 ERR-ANALYS DATA UNCERTAINTIES GIVEN ARE STANDARD DEVIATIONS AND DO13345 4 12 NOT INCLUDE 5-10% UNCERTAINTY IN THE NORMALIZATION OF 13345 4 13 THE MASS YIELD CURVE 13345 4 14 ENDBIB 12 13345 4 15 NOCOMMON 0 0 13345 4 16 DATA 4 1 13345 4 17 MASS DATA DATA-ERR MONIT 13345 4 18 NO-DIM PC/FIS PC/FIS PC/FIS 13345 4 19 115. 0.0134 0.0013 0.0132 13345 4 20 ENDDATA 3 13345 4 21 ENDSUBENT 4 13345 499999 SUBENT 13345005 891128 13345 5 1 BIB 6 10 13345 5 2 REACTION (92-U-234(N,F)41-NB-96,IND,FY) 13345 5 3 SAMPLE U(3)O(8) SAMPLE. ISOTOPIC COMPOSITION: 234U (99.33%), 13345 5 4 233U (<.0005%), 235U (0.36%), 236U (0.11%), 13345 5 5 238U (0.20%) 13345 5 6 DETECTOR (GELI) 13345 5 7 MONITOR (92-U-234(N,F)60-ND-147,CUM,FY) 13345 5 8 DECAY-DATA (41-NB-96,0.975D,DG,778.,0.97) 13345 5 9 ERR-ANALYS DATA UNCERTAINTIES GIVEN ARE STANDARD DEVIATIONS AND DO13345 5 10 NOT INCLUDE 5-10% UNCERTAINTY IN THE NORMALIZATION OF 13345 5 11 THE MASS YIELD CURVE 13345 5 12 ENDBIB 10 13345 5 13 NOCOMMON 0 0 13345 5 14 DATA 3 1 13345 5 15 DATA DATA-ERR MONIT 13345 5 16 PC/FIS PC/FIS PC/FIS 13345 5 17 8.0E-5 0.3E-5 0.0132 13345 5 18 ENDDATA 3 13345 5 19 ENDSUBENT 3 13345 599999 SUBENT 13345006 891128 13345 6 1 BIB 6 10 13345 6 2 REACTION (92-U-234(N,F)55-CS-136,IND,FY) 13345 6 3 SAMPLE U(3)O(8) SAMPLE. ISOTOPIC COMPOSITION: 234U (99.33%), 13345 6 4 233U (<.0005%), 235U (0.36%), 236U (0.11%), 13345 6 5 238U (0.20%) 13345 6 6 DETECTOR (NAICR) 13345 6 7 MONITOR (92-U-234(N,F)60-ND-147,CUM,FY) 13345 6 8 DECAY-DATA (55-CS-136,13.0D,DG,818.,1.00) 13345 6 9 ERR-ANALYS DATA UNCERTAINTIES GIVEN ARE STANDARD DEVIATIONS AND DO13345 6 10 NOT INCLUDE 5-10% UNCERTAINTY IN THE NORMALIZATION OF 13345 6 11 THE MASS YIELD CURVE 13345 6 12 ENDBIB 10 13345 6 13 NOCOMMON 0 0 13345 6 14 DATA 3 1 13345 6 15 DATA DATA-ERR MONIT 13345 6 16 PC/FIS PC/FIS PC/FIS 13345 6 17 4.91E-3 .20E-3 0.0132 13345 6 18 ENDDATA 3 13345 6 19 ENDSUBENT 3 13345 699999 SUBENT 13345007 900604 13345 7 1 BIB 7 26 13345 7 2 REACTION (92-U-236(N,F)ELEM/MASS,CUM,FY) 13345 7 3 SAMPLE U(3)O(8) SAMPLE. ISOTOPIC COMPOSITION: 236U (99.21%), 13345 7 4 233U (<.0002%), 234U (0.005%), 235U (0.57%), 13345 7 5 238U (0.21%) 13345 7 6 2 METAL SAMPLES. ISOTOPIC COMPOSITION: 236U (99.76%), 13345 7 7 235U (0.20%), 238U (0.03%) 13345 7 8 DETECTOR (PROPC) GAS-FLOW BETA PROPORTIONAL COUNTERS 13345 7 9 MONITOR (92-U-236(N,F)60-ND-147,CUM,FY) 13345 7 10 DECAY-DATA ((1.)28-NI-66,2.29D,B) 13345 7 11 ((2.)29-CU-67,2.56D,B) 13345 7 12 ((3.)30-ZN-72,1.942D,B) 13345 7 13 ((4.)38-SR-89,50.6D,B) 13345 7 14 ((5.)39-Y-91,58.8D,B) 13345 7 15 ((6.)39-Y-93,0.427D,B) 13345 7 16 ((7.)58-CE-141,32.4D,B) 13345 7 17 ((8.)58-CE-144,284.0D,B) 13345 7 18 ((9.)62-SM-153,1.928D,B) 13345 7 19 ((10.)64-GD-159,0.773D,B) 13345 7 20 ((11.)65-TB-161,6.96D,B) 13345 7 21 ((12.)66-DY-166,3.40D,B) 13345 7 22 ((13.)68-ER-169,9.5D,B) 13345 7 23 ((14.)68-ER-172,2.08D,B) 13345 7 24 ERR-ANALYS DATA UNCERTAINTIES GIVEN ARE STANDARD DEVIATIONS AND DO13345 7 25 NOT INCLUDE ABOUT 6% UNCERTAINTY IN THE NORMALIZATION 13345 7 26 OF THE MASS YIELD CURVE 13345 7 27 HISTORY (900604A) ELEMENT ADDED TO DATA TABLE 13345 7 28 ENDBIB 26 13345 7 29 COMMON 1 3 13345 7 30 MONIT 13345 7 31 PC/FIS 13345 7 32 0.0179 13345 7 33 ENDCOMMON 1 3 13345 7 34 DATA 5 14 13345 7 35 MASS ELEMENT DATA DATA-ERR DECAY-FLAG 13345 7 36 NO-DIM NO-DIM PC/FIS PC/FIS NO-DIM 13345 7 37 66. 28. 1.91 -06 0.19 -06 1. 13345 7 38 67. 29. 4.2 -06 0.4 -06 2. 13345 7 39 72. 30. 4.82 -05 0.15 -05 3. 13345 7 40 89. 38. 0.0378 0.0019 4. 13345 7 41 91. 39. 0.044 0.005 5. 13345 7 42 93. 39. 0.052 0.005 6. 13345 7 43 141. 58. 0.042 0.003 7. 13345 7 44 144. 58. 0.0361 0.0024 8. 13345 7 45 153. 62. 2.90 -03 0.24 -03 9. 13345 7 46 159. 64. 1.69 -04 0.17 -0410. 13345 7 47 161. 65. 6.7 -05 0.4 -0511. 13345 7 48 166. 66. 4.3 -06 0.3 -0612. 13345 7 49 169. 68. 1.24 -06 0.26 -0613. 13345 7 50 172. 68. 1.4 -07 0.6 -0714. 13345 7 51 ENDDATA 16 13345 7 52 ENDSUBENT 5 13345 799999 SUBENT 13345008 900604 13345 8 1 BIB 7 24 13345 8 2 REACTION (92-U-236(N,F)ELEM/MASS,CUM,FY) 13345 8 3 SAMPLE U(3)O(8) SAMPLE. ISOTOPIC COMPOSITION: 236U (99.21%), 13345 8 4 233U (<.0002%), 234U (0.005%), 235U (0.57%), 13345 8 5 238U (0.21%) 13345 8 6 2 METAL SAMPLES. ISOTOPIC COMPOSITION: 236U (99.76%), 13345 8 7 235U (0.20%), 238U (0.03%) 13345 8 8 DETECTOR (NAICR) 13345 8 9 MONITOR (92-U-236(N,F)60-ND-147,CUM,FY) 13345 8 10 DECAY-DATA ((1.)40-ZR-95,65.D,DG,765.,0.99) 13345 8 11 ((2.)40-ZR-97,0.701D,DG,743.,0.94) 13345 8 12 ((3.)42-MO-99,2.752D,DG,739.,0.124) 13345 8 13 ((4.)45-RH-105,1.476D,DG,319.,0.19) 13345 8 14 ((5.)47-AG-111,7.45D,B,,,DG) 13345 8 15 ((6.)46-PD-112,0.875D,DG,617.,0.435) 13345 8 16 ((7.)52-TE-132,3.24D,DG,668.,0.98) 13345 8 17 ((8.)55-CS-137,10960.0D,DG,662.,0.85) 13345 8 18 ((9.)56-BA-140,12.80D,DG,1596.,0.96) 13345 8 19 ((10.)58-CE-143,1.379D,DG,293.,0.47) 13345 8 20 ((11.)60-ND-147,11.04D,DG,531.,0.132) 13345 8 21 ((12.)63-EU-156,15.19D,DG,812.,0.108) 13345 8 22 ERR-ANALYS DATA UNCERTAINTIES GIVEN ARE STANDARD DEVIATIONS AND DO13345 8 23 NOT INCLUDE ABOUT 6% UNCERTAINTY IN THE NORMALIZATION 13345 8 24 OF THE MASS YIELD CURVE 13345 8 25 HISTORY (900604A) ELEMENT ADDED TO DATA TABLE, BIB CORRECTION. 13345 8 26 ENDBIB 24 13345 8 27 COMMON 1 3 13345 8 28 MONIT 13345 8 29 PC/FIS 13345 8 30 0.0179 13345 8 31 ENDCOMMON 1 3 13345 8 32 DATA 5 12 13345 8 33 MASS ELEMENT DATA DATA-ERR DECAY-FLAG 13345 8 34 NO-DIM NO-DIM PC/FIS PC/FIS NO-DIM 13345 8 35 95. 40. 0.0544 0.0022 1. 13345 8 36 97. 40. 0.056 0.004 2. 13345 8 37 99. 42. 0.053 0.005 3. 13345 8 38 105. 45. 0.0259 0.0021 4. 13345 8 39 111. 47. 0.0112 0.0005 5. 13345 8 40 112. 46. 0.0120 0.0006 6. 13345 8 41 132. 52. 0.047 0.005 7. 13345 8 42 137. 55. 0.0531 0.0022 8. 13345 8 43 140. 56. 0.0425 0.0018 9. 13345 8 44 143. 58. 0.0408 0.0021 10. 13345 8 45 147. 60. 0.0179 0.0010 11. 13345 8 46 156. 63. 7.3 -04 0.3 -0412. 13345 8 47 ENDDATA 14 13345 8 48 ENDSUBENT 5 13345 899999 SUBENT 13345009 891128 13345 9 1 BIB 6 14 13345 9 2 REACTION (92-U-236(N,F)MASS,CHN,FY) 13345 9 3 THE MEASURED 115M/115G RATIO = 0.0735 13345 9 4 SAMPLE U(3)O(8) SAMPLE. ISOTOPIC COMPOSITION: 236U (99.21%), 13345 9 5 233U (<.0002%), 234U (0.005%), 235U (0.57%), 13345 9 6 238U (0.21%) 13345 9 7 2 METAL SAMPLES. ISOTOPIC COMPOSITION: 236U (99.76%), 13345 9 8 235U (0.20%), 238U (0.03%) 13345 9 9 DETECTOR (GELI) 13345 9 10 MONITOR (92-U-234(N,F)60-ND-147,CUM,FY) 13345 9 11 DECAY-DATA (48-CD-115-G,2.208D,DG,336.,0.50) 13345 9 12 (48-CD-115-M,43.0D,B) 13345 9 13 ERR-ANALYS DATA UNCERTAINTIES GIVEN ARE STANDARD DEVIATIONS AND DO13345 9 14 NOT INCLUDE ABOUT 6% UNCERTAINTY IN THE NORMALIZATION 13345 9 15 OF THE MASS YIELD CURVE 13345 9 16 ENDBIB 14 13345 9 17 NOCOMMON 0 0 13345 9 18 DATA 4 1 13345 9 19 MASS DATA DATA-ERR MONIT 13345 9 20 NO-DIM PC/FIS PC/FIS PC/FIS 13345 9 21 115. 0.0134 0.0013 0.0132 13345 9 22 ENDDATA 3 13345 9 23 ENDSUBENT 4 13345 999999 SUBENT 13345010 891128 13345 10 1 BIB 5 11 13345 10 2 REACTION (92-U-236(N,F)41-NB-96,IND,FY) 13345 10 3 SAMPLE U(3)O(8) SAMPLE. ISOTOPIC COMPOSITION: 236U (99.21%), 13345 10 4 233U (<.0002%), 234U (0.005%), 235U (0.57%), 13345 10 5 238U (0.21%) 13345 10 6 2 METAL SAMPLES. ISOTOPIC COMPOSITION: 236U (99.76%), 13345 10 7 235U (0.20%), 238U (0.03%) 13345 10 8 DETECTOR (GELI) 13345 10 9 DECAY-DATA (41-NB-96,0.975D,DG,778.,0.97) 13345 10 10 ERR-ANALYS DATA UNCERTAINTIES GIVEN ARE STANDARD DEVIATIONS AND DO13345 10 11 NOT INCLUDE ABOUT 6% UNCERTAINTY IN THE NORMALIZATION 13345 10 12 OF THE MASS YIELD CURVE 13345 10 13 ENDBIB 11 13345 10 14 NOCOMMON 0 0 13345 10 15 DATA 2 1 13345 10 16 DATA DATA-ERR 13345 10 17 PC/FIS PC/FIS 13345 10 18 1.45 -05 0.12 -05 13345 10 19 ENDDATA 3 13345 10 20 ENDSUBENT 2 13345 1099999 SUBENT 13345011 891128 13345 11 1 BIB 5 11 13345 11 2 REACTION (92-U-236(N,F)55-CS-136,IND,FY) 13345 11 3 SAMPLE U(3)O(8) SAMPLE. ISOTOPIC COMPOSITION: 236U (99.21%), 13345 11 4 233U (<.0002%), 234U (0.005%), 235U (0.57%), 13345 11 5 238U (0.21%) 13345 11 6 2 METAL SAMPLES. ISOTOPIC COMPOSITION: 236U (99.76%), 13345 11 7 235U (0.20%), 238U (0.03%) 13345 11 8 DETECTOR (NAICR) 13345 11 9 DECAY-DATA (55-CS-136,13.0D,DG,818.,1.00) 13345 11 10 ERR-ANALYS DATA UNCERTAINTIES GIVEN ARE STANDARD DEVIATIONS AND DO13345 11 11 NOT INCLUDE ABOUT 6% UNCERTAINTY IN THE NORMALIZATION 13345 11 12 OF THE MASS YIELD CURVE 13345 11 13 ENDBIB 11 13345 11 14 NOCOMMON 0 0 13345 11 15 DATA 2 1 13345 11 16 DATA DATA-ERR 13345 11 17 PC/FIS PC/FIS 13345 11 18 1.20 -03 0.05 -03 13345 11 19 ENDDATA 3 13345 11 20 ENDSUBENT 2 13345 1199999 ENDENTRY 11 1334599999999 ENTRY 13346 891128 13346 0 1 SUBENT 13346001 891128 13346 1 1 BIB 12 20 13346 1 2 INSTITUTE (1USALRL) 13346 1 3 REFERENCE (J,PR/C,2,2289,7012) 13346 1 4 (J,PR/C,6,1827,7211) REVISED DATA 13346 1 5 AUTHOR (D.R.NETHAWAY,B.MENDOZA) 13346 1 6 TITLE FISSION OF 233U WITH 14.8 MEV NEUTRINS 13346 1 7 FACILITY (ICTR) 13346 1 8 INC-SOURCE (D-T) 13346 1 9 SAMPLE METAL FOILS. ISOTOPIC COMPOSITION: 223U (97.5%), 13346 1 10 234U(1.1%), 235U (250PPM), 236U (20PPM), 238U (1.4%) 13346 1 11 METHOD (RCHEM) 13346 1 12 ASSUMED (ASSUM,92-U-233(N,F),,SIG) 13346 1 13 ERR-ANALYS DATA UNCERTAINTY GIVEN INCLUDES UNCERTAINTY IN: 13346 1 14 - COUNTING EFFICIENCY 13346 1 15 - COUNTING STATISTICS 13346 1 16 - AGREEMENT BETWEEN REPLICATE MEASUREMENTS 13346 1 17 DOES NOT INCLUDE 6% UNCERTAINTY IN IN NUMBER OF 13346 1 18 FISSIONS 13346 1 19 STATUS (RIDER) REFERENCE 72NET2 13346 1 20 DATA TAKEN FROM PHYS.REV.C 6, 1827 (1972) 13346 1 21 HISTORY (891026C) VM 13346 1 22 ENDBIB 20 13346 1 23 COMMON 4 3 13346 1 24 EN EN-RSL ASSUM ASSUM-ERR 13346 1 25 MEV MEV B B 13346 1 26 14.8 0.3 2.40 0.06 13346 1 27 ENDCOMMON 4 3 13346 1 28 ENDSUBENT 4 13346 199999 SUBENT 13346002 891128 13346 2 1 BIB 2 2 13346 2 2 REACTION (92-U-233(N,F)ELEM/MASS,CUM,FY) 13346 2 3 MONITOR (92-U-233(N,F)40-ZR-97,CUM,FY) 13346 2 4 ENDBIB 2 13346 2 5 COMMON 1 3 13346 2 6 MONIT 13346 2 7 PC/FIS 13346 2 8 0.048 13346 2 9 ENDCOMMON 1 3 13346 2 10 DATA 4 24 13346 2 11 MASS ELEMENT DATA DATA-ERR 13346 2 12 NO-DIM NO-DIM PC/FIS PC/FIS 13346 2 13 66. 28. 7.1 -06 0.7 -06 13346 2 14 67. 29. 1.64E -05 0.19 -05 13346 2 15 72. 30. 1.35E -04 0.06 -04 13346 2 16 93. 39. 0.055 0.006 13346 2 17 95. 40. 0.052 0.002 13346 2 18 97. 40. 0.048 0.003 13346 2 19 99. 42. 0.038 0.003 13346 2 20 105. 45. 0.0204 0.0019 13346 2 21 111. 47. 0.0164 0.0007 13346 2 22 112. 46. 0.0175 0.0011 13346 2 23 115. 48. 0.0155 0.0016 13346 2 24 132. 52. 0.032 0.003 13346 2 25 140. 56. 0.0401 0.0016 13346 2 26 141. 58. 0.042 0.003 13346 2 27 143. 58. 0.0328 0.0017 13346 2 28 144. 58. 0.0249 0.0016 13346 2 29 147. 60. 0.0119 0.0008 13346 2 30 153. 62. 1.44 -03 0.12 -03 13346 2 31 159. 64. 1.07 -04 0.11 -04 13346 2 32 161. 65. 4.7 -05 0.3 -05 13346 2 33 166. 66. 2.4 -06 0.2 -06 13346 2 34 169. 68. 8.4 -07 0.6 -07 13346 2 35 172. 68. 1.81 -07 0.15 -08 13346 2 36 175. 70. 1.9 -08 0.3 -08 13346 2 37 ENDDATA 26 13346 2 38 ENDSUBENT 4 13346 299999 SUBENT 13346003 891128 13346 3 1 BIB 3 3 13346 3 2 REACTION (92-U-233(N,F)ELEM/MASS,CUM,FY) 13346 3 3 MONITOR (92-U-233(N,F)40-ZR-97,CUM,FY) 13346 3 4 STATUS NEW RESULTS WITH SAME EXPERIMENTAL CONDITIONS 13346 3 5 ENDBIB 3 13346 3 6 COMMON 1 3 13346 3 7 MONIT 13346 3 8 PC/FIS 13346 3 9 0.048 13346 3 10 ENDCOMMON 1 3 13346 3 11 DATA 4 4 13346 3 12 MASS ELEMENT DATA DATA-ERR 13346 3 13 NO-DIM NO-DIM PC/FIS PC/FIS 13346 3 14 96. 41. 2.0 -04 0.2 -04 13346 3 15 136. 55. 9.2 -03 0.4 -03 13346 3 16 137. 55. 0.051 0.002 13346 3 17 156. 63. 4.4 -04 0.2 -04 13346 3 18 ENDDATA 6 13346 3 19 ENDSUBENT 4 13346 399999 SUBENT 13346004 891128 13346 4 1 BIB 2 2 13346 4 2 REACTION (92-U-233(N,F)65-TB-160,IND,FY) 13346 4 3 MONITOR (92-U-233(N,F)40-ZR-97,CUM,FY) 13346 4 4 ENDBIB 2 13346 4 5 COMMON 1 3 13346 4 6 MONIT 13346 4 7 PC/FIS 13346 4 8 0.048 13346 4 9 ENDCOMMON 1 3 13346 4 10 DATA 2 1 13346 4 11 DATA DATA-ERR 13346 4 12 PC/FIS PC/FIS 13346 4 13 3.0 -07 0.8 -07 13346 4 14 ENDDATA 3 13346 4 15 ENDSUBENT 2 13346 499999 ENDENTRY 4 1334699999999 ENTRY 13347 891128 13347 0 1 SUBENT 13347001 891128 13347 1 1 BIB 8 9 13347 1 2 INSTITUTE (1USALRL) 13347 1 3 REFERENCE (W,PRINDLE,72) TO NETHAWAY, SEE PHYS.REV C 6,1827 13347 1 4 (1972) 13347 1 5 AUTHOR (A.PRINDLE) 13347 1 6 METHOD (RCHEM) 13347 1 7 DETECTOR (GELI) 13347 1 8 ERR-ANALYS NO INFORMATION 13347 1 9 STATUS (RIDER) REFERENCE 72PRI1 13347 1 10 HISTORY (891026C) VM 13347 1 11 ENDBIB 9 13347 1 12 COMMON 1 3 13347 1 13 EN 13347 1 14 MEV 13347 1 15 14.8 13347 1 16 ENDCOMMON 1 3 13347 1 17 ENDSUBENT 1 13347 199999 SUBENT 13347002 891128 13347 2 1 BIB 3 5 13347 2 2 REACTION 1((92-U-235(N,F)ELEM/MASS,IND,FY)/ 13347 2 3 (92-U-235(N,F)MASS,CHN,FY)) 13347 2 4 2(92-U-235(N,F)ELEM/MASS,IND,FY) 13347 2 5 RESULT 1(FRIND) 13347 2 6 STATUS INDEPENDENT YIELD INCORRECTLY QUOTED BY NETHAWAY 13347 2 7 ENDBIB 5 13347 2 8 NOCOMMON 0 0 13347 2 9 DATA 6 1 13347 2 10 ELEMENT MASS DATA 1DATA-ERR 1DATA 2DATA-ERR 213347 2 11 NO-DIM NO-DIM NO-DIM NO-DIM PC/FIS PC/FIS 13347 2 12 55. 136. 0.048 0.003 0.247 0.012 13347 2 13 ENDDATA 3 13347 2 14 ENDSUBENT 6 13347 299999 SUBENT 13347003 891128 13347 3 1 BIB 2 4 13347 3 2 REACTION 1((92-U-238(N,F)ELEM/MASS,IND,FY)/ 13347 3 3 (92-U-238(N,F)MASS,CHN,FY)) 13347 3 4 2(92-U-238(N,F)ELEM/MASS,IND,FY) 13347 3 5 RESULT 1(FRIND) 13347 3 6 ENDBIB 4 13347 3 7 NOCOMMON 0 0 13347 3 8 DATA 6 1 13347 3 9 ELEMENT MASS DATA 1DATA-ERR 1DATA 2DATA-ERR 213347 3 10 NO-DIM NO-DIM NO-DIM NO-DIM PC/FIS PC/FIS 13347 3 11 55. 136. 3.7 -03 0.3 -03 2.19 -04 0.10 -0413347 3 12 ENDDATA 3 13347 3 13 ENDSUBENT 6 13347 399999 SUBENT 13347004 891128 13347 4 1 BIB 2 3 13347 4 2 REACTION ((94-PU-239(N,F)ELEM/MASS,IND,FY)/ 13347 4 3 (94-PU-239(N,F)MASS,CHN,FY)) 13347 4 4 RESULT (FRIND) 13347 4 5 ENDBIB 3 13347 4 6 NOCOMMON 0 0 13347 4 7 DATA 4 1 13347 4 8 ELEMENT MASS DATA DATA-ERR 13347 4 9 NO-DIM NO-DIM NO-DIM NO-DIM 13347 4 10 55. 136. 0.151 0.008 13347 4 11 ENDDATA 3 13347 4 12 ENDSUBENT 4 13347 499999 ENDENTRY 4 1334799999999 ENTRY 13368 891220 13368 0 1 SUBENT 13368001 891220 13368 1 1 BIB 6 7 13368 1 2 INSTITUTE (1USALAS) 13368 1 3 REFERENCE (J,PR,85,570,5202) 13368 1 4 AUTHOR (A.C.WAHL,N.A.BONNER) 13368 1 5 TITLE GENETIC RELATIONSHIPS AND FISSION YIELDS OF MEMBERS OF 13368 1 6 THE MASS-115 DECAY CHAIN 13368 1 7 STATUS (RIDER) 52WAH1 13368 1 8 HISTORY (891211C) VM 13368 1 9 ENDBIB 7 13368 1 10 NOCOMMON 0 0 13368 1 11 ENDSUBENT 0 13368 199999 SUBENT 13368004 891220 13368 4 1 BIB 3 4 13368 4 2 REACTION (92-U-235(N,F)ELEM/MASS,CUM,FY) 13368 4 3 FACILITY (CCW) 13368 4 4 DECAY-DATA ((1.)48-CD-115-G,53.HR) 13368 4 5 ((2.)48-CD-115-M,43.D) 13368 4 6 ENDBIB 4 13368 4 7 COMMON 4 3 13368 4 8 EN ELEMENT MASS DATA-ERR 13368 4 9 MEV NO-DIM NO-DIM PER-CENT 13368 4 10 14. 48. 115. 10. 13368 4 11 ENDCOMMON 4 3 13368 4 12 DATA 3 2 13368 4 13 ISOMER DATA DECAY-FLAG 13368 4 14 NO-DIM PC/FIS NO-DIM 13368 4 15 0. 0.98 1. 13368 4 16 1. 0.069 2. 13368 4 17 ENDDATA 4 13368 4 18 ENDSUBENT 3 13368 499999 ENDENTRY 2 1336899999999 ENTRY 13374 891220 13374 0 1 SUBENT 13374001 891220 13374 1 1 BIB 8 8 13374 1 2 INSTITUTE (1USALAS) 13374 1 3 REFERENCE (J,PR,92,1091(I4),5311) ABSTRACT. 13374 1 4 AUTHOR (J.TERRELL,W.E.SCOTT,J.S.GILMORE,C.O.MINKKINEN) 13374 1 5 TITLE YIELDS OF MO99 FROM FISSION OF U-235 AND U-238 13374 1 6 METHOD (RCHEM) 13374 1 7 ERR-ANALYS (DATA-ERR) STANDARD DEVIATIONS 13374 1 8 STATUS (RIDER) 53TER1 13374 1 9 HISTORY (891211C) VM 13374 1 10 ENDBIB 8 13374 1 11 NOCOMMON 0 0 13374 1 12 ENDSUBENT 0 13374 199999 SUBENT 13374004 891220 13374 4 1 BIB 2 2 13374 4 2 REACTION (92-U-238(N,F)42-MO-99,CUM,FY) 13374 4 3 INC-SOURCE P-T, D-D, AND D-T SOURCES 13374 4 4 ENDBIB 2 13374 4 5 NOCOMMON 0 0 13374 4 6 DATA 3 1 13374 4 7 EN DATA DATA-ERR 13374 4 8 MEV PC/FIS PC/FIS 13374 4 9 14.2 5.68 0.14 13374 4 10 ENDDATA 3 13374 4 11 ENDSUBENT 3 13374 499999 ENDENTRY 2 1337499999999 ENTRY 13388 891220 13388 0 1 SUBENT 13388001 891220 13388 1 1 BIB 9 11 13388 1 2 INSTITUTE (1USALAS) 13388 1 3 REFERENCE (J,PR,99,730,5508) 13388 1 4 AUTHOR (A.C.WAHL) 13388 1 5 TITLE FISSION OF U-235 BY 14-MEV NEUTRONS: NUCLEAR CHARGE 13388 1 6 DISTRIBUTIONS AND YIELD FINE STRUCTURE 13388 1 7 METHOD (RCHEM) 13388 1 8 DETECTOR (PROPC) 13388 1 9 ERR-ANALYS (DATA-ERR) STANDARD DEVIATION OF THE AVERAGE OF THE 13388 1 10 RESULTS 13388 1 11 STATUS (RIDER) 13388 1 12 HISTORY (891212C) VM 13388 1 13 ENDBIB 11 13388 1 14 NOCOMMON 0 0 13388 1 15 ENDSUBENT 0 13388 199999 SUBENT 13388002 891220 13388 2 1 BIB 3 12 13388 2 2 REACTION ((92-U-235(N,F)ELEM/MASS,CUM,FY)// 13388 2 3 (92-U-235(N,F)ELEM/MASS,CUM,FY,,SPA)) 13388 2 4 MONITOR ((MONIT1)92-U-235(N,F)42-MO-99,CUM,FY) 13388 2 5 ((MONIT2)92-U-235(N,F)42-MO-99,CUM,FY,,SPA) 13388 2 6 DECAY-DATA ((1.)52-TE-131-M,30.HR) 13388 2 7 ((2.)53-I-131,8.07D,B-) 13388 2 8 ((3.)52-TE-132,77.7HR) 13388 2 9 ((4.)53-I-132,2.3HR,B-) 13388 2 10 ((5.)52-TE-133-M,63.MIN) 13388 2 11 ((6.)53-I-133,20.9HR,B-) 13388 2 12 ((7.)53-I-134,52.5MIN,B-) 13388 2 13 ((8.)53-I-135,6.7HR,B-) 13388 2 14 ENDBIB 12 13388 2 15 COMMON 4 3 13388 2 16 EN-NM EN-DUM-DN MONIT1 MONIT2 13388 2 17 MEV EV PC/FIS PC/FIS 13388 2 18 14. 0.0253 5.17 6.14 13388 2 19 ENDCOMMON 4 3 13388 2 20 DATA 6 8 13388 2 21 MASS ELEMENT ISOMER DATA DATA-ERR DECAY-FLAG 13388 2 22 NO-DIM NO-DIM NO-DIM NO-DIM NO-DIM NO-DIM 13388 2 23 131. 52. 1. 5.5 1.5 1. 13388 2 24 131. 53. 1.48 0.07 2. 13388 2 25 132. 52. 0.97 0.02 3. 13388 2 26 132. 53. 1.12 0.02 4. 13388 2 27 133. 52. 1. 0.64 0.15 5. 13388 2 28 133. 53. 0.81 0.03 6. 13388 2 29 134. 53. 0.65 0.02 7. 13388 2 30 135. 53. 0.69 0.02 8. 13388 2 31 ENDDATA 10 13388 2 32 ENDSUBENT 6 13388 299999 SUBENT 13388003 891220 13388 3 1 BIB 6 12 13388 3 2 REACTION (92-U-235(N,F)ELEM/MASS,IND,FY) 13388 3 3 FACILITY (CCW) 13388 3 4 INC-SOURCE (D-T) 13388 3 5 MONITOR ((MONIT1)92-U-235(N,F)42-MO-99,CUM,FY) 13388 3 6 ((MONIT2)92-U-235(N,F)42-MO-99,CUM,FY,,SPA) 13388 3 7 ((MONIT3)92-U-235(N,F)ELEM/MASS,CUM,FY,,SPA) 13388 3 8 DECAY-DATA ((1.)53-I-131,8.07D,B-) 13388 3 9 ((2.)53-I-132,2.3HR,B-) 13388 3 10 ((3.)53-I-133,20.9HR,B-) 13388 3 11 ((4.)53-I-134,52.5MIN,B-) 13388 3 12 ((5.)53-I-135,6.7HR,B-) 13388 3 13 STATUS (DEP,13388002) 13388 3 14 ENDBIB 12 13388 3 15 COMMON 4 3 13388 3 16 EN EN-NRM MONIT1 MONIT2 13388 3 17 MEV EV PC/FIS PC/FIS 13388 3 18 14. 0.0253 5.17 6.14 13388 3 19 ENDCOMMON 4 3 13388 3 20 DATA 5 5 13388 3 21 MASS ELEMENT DATA MONIT3 DECAY-FLAG 13388 3 22 NO-DIM NO-DIM PC/FIS PC/FIS NO-DIM 13388 3 23 131. 53. 4.47 3.02 1. 13388 3 24 132. 53. 5.03 4.49 2. 13388 3 25 133. 53. 5.36 6.62 3. 13388 3 26 134. 53. 5.20 8.00 4. 13388 3 27 135. 53. 4.35 6.31 5. 13388 3 28 ENDDATA 7 13388 3 29 ENDSUBENT 5 13388 399999 SUBENT 13388004 891220 13388 4 1 BIB 4 5 13388 4 2 REACTION ((92-U-235(N,F)ELEM/MASS,IND,FY)/ 13388 4 3 (92-U-235(N,F)MASS,CHN,FY)) 13388 4 4 RESULT (FRIND) 13388 4 5 FACILITY (CCW) 13388 4 6 INC-SOURCE (D-T) 13388 4 7 ENDBIB 5 13388 4 8 COMMON 1 3 13388 4 9 EN 13388 4 10 MEV 13388 4 11 14. 13388 4 12 ENDCOMMON 1 3 13388 4 13 DATA 6 6 13388 4 14 MASS ELEMENT ISOMER DATA DATA-ERR DATA-MAX 13388 4 15 NO-DIM NO-DIM NO-DIM NO-DIM NO-DIM NO-DIM 13388 4 16 131. 52. 1. 0.35 0.05 13388 4 17 131. 53. 0.08 13388 4 18 132. 53. 0.16 0.01 13388 4 19 133. 52. 0.40 13388 4 20 133. 53. 0.40 13388 4 21 134. 53. 0.43 0.02 13388 4 22 ENDDATA 8 13388 4 23 ENDSUBENT 6 13388 499999 ENDENTRY 4 1338899999999 ENTRY 13432 900207 13432 0 1 SUBENT 13432001 900207 13432 1 1 BIB 8 8 13432 1 2 INSTITUTE (1USALAS) 13432 1 3 REFERENCE ((R,TID-5787,57)=(R,LADC-3083,57)) 13432 1 4 AUTHOR (B.P.BAYHURST) 13432 1 5 TITLE FISSION YIELDS OF SR90 13432 1 6 DECAY-DATA (38-SR-90,28.YR) 13432 1 7 ERR-ANALYS NO INFORMATION 13432 1 8 STATUS (RIDER) 13432 1 9 HISTORY (900111C) VM 13432 1 10 ENDBIB 8 13432 1 11 NOCOMMON 0 0 13432 1 12 ENDSUBENT 0 13432 199999 SUBENT 13432003 900207 13432 3 1 BIB 3 3 13432 3 2 REACTION (92-U-235(N,F)38-SR-90,CUM,FY) 13432 3 3 FACILITY (CCW) 13432 3 4 MONITOR (92-U-235(N,F)42-MO-99,CUM,FY) 13432 3 5 ENDBIB 3 13432 3 6 NOCOMMON 0 0 13432 3 7 DATA 3 1 13432 3 8 EN DATA DATA-ERR 13432 3 9 MEV PC/FIS PC/FIS 13432 3 10 14. 4.40 0.17 13432 3 11 ENDDATA 3 13432 3 12 ENDSUBENT 3 13432 399999 SUBENT 13432004 900207 13432 4 1 BIB 2 2 13432 4 2 REACTION (92-U-238(N,F)38-SR-90,CUM,FY) 13432 4 3 FACILITY (CCW) 13432 4 4 ENDBIB 2 13432 4 5 NOCOMMON 0 0 13432 4 6 DATA 3 1 13432 4 7 EN DATA DATA-ERR 13432 4 8 MEV PC/FIS PC/FIS 13432 4 9 14. 3.06 0.12 13432 4 10 ENDDATA 3 13432 4 11 ENDSUBENT 3 13432 499999 ENDENTRY 3 1343299999999 ENTRY 13441 900604 13441 0 1 SUBENT 13441001 891122 13441 1 1 BIB 6 6 13441 1 2 INSTITUTE (1USALAS) 13441 1 3 REFERENCE (W,WOLFSBERG,7310) TO B. F. RIDER 13441 1 4 AUTHOR (K.WOLFSBERG,G.P.FORD,B.R.ERDAL) 13441 1 5 METHOD (RCHEM) 13441 1 6 STATUS (RIDER) REFERENCE 73WOL1 13441 1 7 HISTORY (891129C) VM 13441 1 8 ENDBIB 6 13441 1 9 NOCOMMON 0 0 13441 1 10 ENDSUBENT 0 13441 199999 SUBENT 13441002 900604 13441 2 1 BIB 4 5 13441 2 2 REACTION ((90-TH-232(N,F)ELEM/MASS,IND,FY)/ 13441 2 3 (90-TH-232(N,F)MASS,CHN,FY)) 13441 2 4 RESULT (FRIND) 13441 2 5 ERR-ANALYS NO INFORMATION 13441 2 6 HISTORY (900604A) DATA CORRECTED, BIB UPDATE 13441 2 7 ENDBIB 5 13441 2 8 COMMON 1 3 13441 2 9 EN 13441 2 10 EV 13441 2 11 14. E+06 13441 2 12 ENDCOMMON 1 3 13441 2 13 DATA 5 2 13441 2 14 ELEMENT MASS ISOMER DATA DATA-MAX 13441 2 15 NO-DIM NO-DIM NO-DIM NO-DIM NO-DIM 13441 2 16 41. 96. 3.0E-5 13441 2 17 47. 110. 1. 1.00E-4 13441 2 18 ENDDATA 4 13441 2 19 ENDSUBENT 5 13441 299999 ENDENTRY 2 1344199999999 ENTRY 13444 900604 13444 0 1 SUBENT 13444001 891220 13444 1 1 BIB 11 14 13444 1 2 INSTITUTE (1USALAS) 13444 1 3 REFERENCE (R,LA-6129,7602) DATA COMPILATION 13444 1 4 (R,LA-1997,5602) 13444 1 5 AUTHOR (G.P.FORD,A.E.NORRIS) 13444 1 6 TITLE A COMPILATION OF YIELDS FROM NEUTRON-INDUCED FISSION 13444 1 7 OF 232TH, 235U, 236U, 237NP, 238U, AND 239PU 13444 1 8 MEASURED RADIOCHEMICALLY AT LOS ALAMOS 13444 1 9 FACILITY (CCW) 13444 1 10 INC-SOURCE (D-T) 13444 1 11 INC-SPECT INCUDENT NEUTRON SPREAD FROM 13.4 TO 15.2 MEV 13444 1 12 METHOD (RCHEM) 13444 1 13 ERR-ANALYS (DATA-ERR) STATISTICAL UNCERTAINTY 13444 1 14 STATUS DATA TAKEN FROM LA-6129 13444 1 15 HISTORY (900111C) VM 13444 1 16 ENDBIB 14 13444 1 17 NOCOMMON 0 0 13444 1 18 ENDSUBENT 0 13444 199999 SUBENT 13444002 891220 13444 2 1 BIB 3 10 13444 2 2 REACTION 1(((90-TH-232(N,F)ELEM/MASS,CUM,FY)/ 13444 2 3 (90-TH-232(N,F)42-MO-99,CUM,FY))// 13444 2 4 ((92-U-235(N,F)ELEM/MASS,CUM,FY,,MXW)/ 13444 2 5 (92-U-235(N,F)42-MO-99,CUM,FY,,MXW))) 13444 2 6 2(90-TH-232(N,F)ELEM/MASS,CUM,FY) 13444 2 7 RESULT 1(RVAL) 13444 2 8 MONITOR 2((MONIT1)(90-TH-232(N,F)42-MO-99,CUM,FY)/ 13444 2 9 (92-U-235(N,F)42-MO-99,CUM,FY,,MXW)) 13444 2 10 ((MONIT2)92-U-235(N,F)ELEM/MASS,CUM,FY,,MXW) 13444 2 11 THERMAL VALUE NOT GIVEN FOR 112PD 13444 2 12 ENDBIB 10 13444 2 13 COMMON 2 3 13444 2 14 EN MONIT1 2 13444 2 15 MEV NO-DIM 13444 2 16 14.7 1.000 13444 2 17 ENDCOMMON 2 3 13444 2 18 DATA 7 5 13444 2 19 MASS ELEMENT ISOMER DATA 1DATA-ERR 1DATA 213444 2 20 MONIT2 2 13444 2 21 NO-DIM NO-DIM NO-DIM NO-DIM PER-CENT PC/FIS 13444 2 22 PC/FIS 13444 2 23 97. 40. 1.37 1.4 8.15 13444 2 24 5.948 13444 2 25 109. 46. 90.9 1.4 2.72 13444 2 26 0.02995 13444 2 27 111. 47. 195.7 2.9 3.868 13444 2 28 0.01976 13444 2 29 112. 46. 220.6 1.3 2.793 13444 2 30 13444 2 31 115. 48. 0. 276.2 1.9 13444 2 32 13444 2 33 ENDDATA 14 13444 2 34 ENDSUBENT 7 13444 299999 SUBENT 13444003 891220 13444 3 1 BIB 3 10 13444 3 2 REACTION 1(((92-U-235(N,F)ELEM/MASS,CUM,FY)/ 13444 3 3 (92-U-235(N,F)42-MO-99,CUM,FY))// 13444 3 4 ((92-U-235(N,F)ELEM/MASS,CUM,FY,,MXW)/ 13444 3 5 (92-U-235(N,F)42-MO-99,CUM,FY,,MXW))) 13444 3 6 2(92-U-235(N,F)ELEM/MASS,CUM,FY) 13444 3 7 RESULT 1(RVAL) 13444 3 8 MONITOR 2((MONIT1)(92-U-235(N,F)42-MO-99,CUM,FY)/ 13444 3 9 (92-U-235(N,F)42-MO-99,CUM,FY,,MXW)) 13444 3 10 ((MONIT2)92-U-235(N,F)ELEM/MASS,CUM,FY,,MXW) 13444 3 11 THERMAL VALUES NOT GIVEN FOR 112PD AND 126SB. 13444 3 12 ENDBIB 10 13444 3 13 COMMON 2 3 13444 3 14 EN MONIT1 2 13444 3 15 MEV NO-DIM 13444 3 16 14.7 0.8780 13444 3 17 ENDCOMMON 2 3 13444 3 18 DATA 7 23 13444 3 19 MASS ELEMENT ISOMER DATA 1DATA-ERR 1DATA 213444 3 20 MONIT2 2 13444 3 21 NO-DIM NO-DIM NO-DIM NO-DIM PER-CENT PC/FIS 13444 3 22 PC/FIS 13444 3 23 83. 35. 2.5 3.0 1.17 13444 3 24 0.5313 13444 3 25 89. 38. 1.09 2.4 4.64 13444 3 26 4.846 13444 3 27 91. 38. 0.99 2.5 5.15 13444 3 28 5.919 13444 3 29 97. 40. 1.05 1.4 5.48 13444 3 30 5.948 13444 3 31 103. 44. 1.38 3.0 3.80 13444 3 32 3.137 13444 3 33 105. 45. 2.41 3.0 2.16 13444 3 34 1.020 13444 3 35 106. 44. 4.86 3.0 1.67 13444 3 36 0.3912 13444 3 37 109. 46. 51.0 1.4 1.34 13444 3 38 0.02995 13444 3 39 111. 47. 76.3 2.9 1.32 13444 3 40 0.01976 13444 3 41 112. 46. 94.7 1.3 1.05 13444 3 42 13444 3 43 115. 48. 0. 101.4 1.9 13444 3 44 13444 3 45 121. 50. 0. 96. 3.0 13444 3 46 13444 3 47 125. 50. 0. 74.6 3.0 13444 3 48 13444 3 49 126. 51. 0. 38. 3.0 1.93 13444 3 50 13444 3 51 127. 51. 20.6 3.0 2.36 13444 3 52 0.1303 13444 3 53 129. 51. 2.7 3.0 1.51 13444 3 54 0.6354 13444 3 55 131. 53. 1.62 2.2 4.03 13444 3 56 2.836 13444 3 57 132. 52. 1.13 3.83 4.20 13444 3 58 4.231 13444 3 59 139. 56. 0.89 3.0 5.07 13444 3 60 6.486 13444 3 61 140. 56. 0.86 1.5 4.77 13444 3 62 6.320 13444 3 63 143. 58. 0.77 0.8 4.04 13444 3 64 5.972 13444 3 65 144. 58. 0.69 4.5 3.31 13444 3 66 5.457 13444 3 67 156. 63. 4.6 1.7 0.055 13444 3 68 0.01351 13444 3 69 ENDDATA 50 13444 3 70 ENDSUBENT 7 13444 399999 SUBENT 13444004 900604 13444 4 1 BIB 4 11 13444 4 2 REACTION 1(((92-U-238(N,F)ELEM/MASS,CUM,FY)/ 13444 4 3 (92-U-238(N,F)42-MO-99,CUM,FY))// 13444 4 4 ((92-U-238(N,F)ELEM/MASS,CUM,FY,,MXW)/ 13444 4 5 (92-U-238(N,F)42-MO-99,CUM,FY,,MXW))) 13444 4 6 2(92-U-238(N,F)ELEM/MASS,CUM,FY) 13444 4 7 RESULT 1(RVAL) 13444 4 8 MONITOR 2((MONIT1)(92-U-238(N,F)42-MO-99,CUM,FY)/ 13444 4 9 (92-U-235(N,F)42-MO-99,CUM,FY,,MXW)) 13444 4 10 ((MONIT2)92-U-235(N,F)ELEM/MASS,CUM,FY,,MXW) 13444 4 11 VALUES FOR 136CS NOT GIVEN 13444 4 12 HISTORY (900604A) DATA HEADINGS CORRECTED 13444 4 13 ENDBIB 11 13444 4 14 COMMON 2 3 13444 4 15 EN MONIT1 2 13444 4 16 MEV NO-DIM 13444 4 17 14.7 0.9252 13444 4 18 ENDCOMMON 2 3 13444 4 19 DATA 7 12 13444 4 20 MASS ELEMENT ISOMER DATA 1DATA-ERR 1DATA 213444 4 21 MONIT2 2 13444 4 22 NO-DIM NO-DIM NO-DIM NO-DIM PER-CENT PC/FIS 13444 4 23 PC/FIS 13444 4 24 89. 38. 0.69 2.4 3.31 13444 4 25 4.846 13444 4 26 97. 40. 0.94 1.4 5.53 13444 4 27 5.948 13444 4 28 105. 45. 3.98 3.08 4.02 13444 4 29 1.020 13444 4 30 111. 47. 65.8 2.9 1.29 13444 4 31 0.01976 13444 4 32 115. 48. 0. 74. 1.9 13444 4 33 13444 4 34 121. 50. 69. 3.0 13444 4 35 13444 4 36 125. 50. 36. 3.0 13444 4 37 13444 4 38 127. 51. 14.1 3.0 1.82 13444 4 39 0.1303 13444 4 40 132. 52. 1.14 3.8 4.77 13444 4 41 4.231 13444 4 42 140. 56. 0.79 1.5 4.94 13444 4 43 6.330 13444 4 44 144. 58. 0.75 4.5 4.05 13444 4 45 5.457 13444 4 46 156. 63. 8.1 1.7 0.108 13444 4 47 0.0135 13444 4 48 ENDDATA 28 13444 4 49 ENDSUBENT 7 13444 499999 SUBENT 13444005 891220 13444 5 1 BIB 3 9 13444 5 2 REACTION 1(((92-U-235(N,F)ELEM/MASS,IND,FY)/ 13444 5 3 (92-U-235(N,F)42-MO-99,CUM,FY))// 13444 5 4 ((92-U-235(N,F)ELEM/MASS,IND,FY,,MXW)/ 13444 5 5 (92-U-235(N,F)42-MO-99,CUM,FY,,MXW))) 13444 5 6 2(92-U-235(N,F)ELEM/MASS,CUM,FY) 13444 5 7 RESULT 1(RVAL) 13444 5 8 MONITOR 2((MONIT1)(92-U-235(N,F)42-MO-99,CUM,FY)/ 13444 5 9 (92-U-235(N,F)42-MO-99,CUM,FY,,MXW)) 13444 5 10 ((MONIT2)92-U-235(N,F)ELEM/MASS,IND,FY,,MXW) 13444 5 11 ENDBIB 9 13444 5 12 COMMON 2 3 13444 5 13 EN MONIT1 2 13444 5 14 MEV PC/FIS 13444 5 15 14.7 0.8780 13444 5 16 ENDCOMMON 2 3 13444 5 17 DATA 6 3 13444 5 18 MASS ELEMENT DATA 1DATA-ERR 2DATA 2MONIT2 213444 5 19 NO-DIM NO-DIM NO-DIM PER-CENT PC/FIS PC/FIS 13444 5 20 82. 35. 44. 3.0 0.00483 1.251 -0413444 5 21 96. 41. 6.0 3.0 0.00316 5.993 -0413444 5 22 136. 55. 46.0 2.7 0.214 5.308 -0413444 5 23 ENDDATA 5 13444 5 24 ENDSUBENT 6 13444 599999 SUBENT 13444006 891220 13444 6 1 BIB 3 9 13444 6 2 REACTION 1(((92-U-238(N,F)55-CS-136,IND,FY)/ 13444 6 3 (92-U-238(N,F)42-MO-99,CUM,FY))// 13444 6 4 ((92-U-238(N,F)55-CS-136,IND,FY,,MXW)/ 13444 6 5 (92-U-235(N,F)42-MO-99,CUM,FY,,MXW))) 13444 6 6 2(92-U-238(N,F)55-CS-136,IND,FY) 13444 6 7 RESULT 1(RVAL) 13444 6 8 MONITOR 2((MONIT1)(92-U-235(N,F)42-MO-99,CUM,FY)/ 13444 6 9 (92-U-235(N,F)42-MO-99,CUM,FY,,MXW)) 13444 6 10 ((MONIT2)92-U-235(N,F)55-CS-136,IND,FY,,MXW) 13444 6 11 ENDBIB 9 13444 6 12 NOCOMMON 0 0 13444 6 13 DATA 6 1 13444 6 14 EN DATA 1DATA-ERR DATA 2MONIT1 2MONIT2 213444 6 15 MEV NO-DIM PER-CENT PC/FIS NO-DIM PC/FIS 13444 6 16 14.7 5.1 2.7 0.0268 0.9252 5.308 -0313444 6 17 ENDDATA 3 13444 6 18 ENDSUBENT 6 13444 699999 SUBENT 13444007 900117 13444 7 1 BIB 3 9 13444 7 2 REACTION 1(((94-PU-239(N,F)ELEM/MASS,CUM,FY)/ 13444 7 3 (94-PU-239(N,F)42-MO-99,CUM,FY))// 13444 7 4 ((92-U-235(N,F)ELEM/MASS,CUM,FY,,MXW)/ 13444 7 5 (92-U-235(N,F)42-MO-99,CUM,FY,,MXW))) 13444 7 6 2(94-PU-239(N,F)ELEM/MASS,CUM,FY) 13444 7 7 RESULT 1(RVAL) 13444 7 8 MONITOR 2((MONIT1)(94-PU-239(N,F)42-MO-99,CUM,FY)/ 13444 7 9 (92-U-235(N,F)42-MO-99,CUM,FY,,MXW)) 13444 7 10 ((MONIT2)92-U-235(N,F)ELEM/MASS,CUM,FY,,MXW) 13444 7 11 ENDBIB 9 13444 7 12 COMMON 2 3 13444 7 13 EN MONIT1 2 13444 7 14 MEV NO-DIM 13444 7 15 14. 0.8835 13444 7 16 ENDCOMMON 2 3 13444 7 17 DATA 7 5 13444 7 18 MASS ELEMENT ISOMER DATA 1DATA-ERR 1DATA 213444 7 19 MONIT2 2 13444 7 20 NO-DIM NO-DIM NO-DIM NO-DIM PER-CENT PC/FIS 13444 7 21 PC/FIS 13444 7 22 97. 40. 0.833 1.4 4.38 13444 7 23 4.846 13444 7 24 109. 46. 94.4 1.4 2.50 13444 7 25 0.02995 13444 7 26 111. 47. 117.1 2.9 2.045 13444 7 27 0.01976 13444 7 28 112. 46. 123.4 1.3 1.380 13444 7 29 13444 7 30 115. 48. 0. 121.8 1.9 13444 7 31 13444 7 32 ENDDATA 14 13444 7 33 ENDSUBENT 7 13444 799999 ENDENTRY 7 1344499999999 ENTRY 13453 900119 13453 0 1 SUBENT 13453001 900119 13453 1 1 BIB 8 9 13453 1 2 INSTITUTE (1USALAS) 13453 1 3 REFERENCE (J,PR,107,325,5707) 13453 1 4 AUTHOR (B.P.BAYHURST,C.I.BROWNE,G.P.FORD,J.S.GILMORE, 13453 1 5 G.W.KNOBELOCH,E.J.LANG,M.A.MELNICK,C.ORTH) 13453 1 6 TITLE RESOANCE FISSION IN U235. 13453 1 7 FACILITY (REAC) WATER BOILER REACTOR 13453 1 8 ERR-ANALYS (DATA-ERR) STANDARD DEVIATION 13453 1 9 STATUS DATA TAKEN FROM ARTICLE 13453 1 10 HISTORY (900119C) VM 13453 1 11 ENDBIB 9 13453 1 12 NOCOMMON 0 0 13453 1 13 ENDSUBENT 0 13453 199999 SUBENT 13453003 900119 13453 3 1 BIB 2 3 13453 3 2 REACTION ((92-U-235(N,F)ELEM/MASS,CUM,FY,,EPI)/ 13453 3 3 (92-U-235(N,F)42-MO-99,CUM,FY,,EPI)) 13453 3 4 INC-SOURCE CADMIUM-WRAPPED SAMPLES. CD RATIO = 8 13453 3 5 ENDBIB 3 13453 3 6 COMMON 1 3 13453 3 7 EN-MIN 13453 3 8 EV 13453 3 9 0.5 13453 3 10 ENDCOMMON 1 3 13453 3 11 DATA 4 6 13453 3 12 MASS ELEMENT DATA DATA-ERR 13453 3 13 NO-DIM NO-DIM NO-DIM NO-DIM 13453 3 14 97. 40. 2.88 3.5 13453 3 15 109. 46. 5.89 -03 1.8 13453 3 16 111. 47. 0.87 -03 0.9 13453 3 17 112. 46. 0.908 -03 0.6 13453 3 18 115. 48. 3.14 -03 2.8 13453 3 19 136. 55. 1.69 -04 0.7 13453 3 20 ENDDATA 8 13453 3 21 ENDSUBENT 4 13453 399999 SUBENT 13453004 900119 13453 4 1 BIB 2 3 13453 4 2 REACTION ((92-U-235(N,F)ELEM/MASS,CUM,FY,,EPI)/ 13453 4 3 (92-U-235(N,F)42-MO-99,CUM,FY,,EPI)) 13453 4 4 INC-SOURCE CADMIUM-WRAPPED SAMPLES. CD RATIO = 30 13453 4 5 ENDBIB 3 13453 4 6 COMMON 1 3 13453 4 7 EN-MIN 13453 4 8 EV 13453 4 9 0.5 13453 4 10 ENDCOMMON 1 3 13453 4 11 DATA 4 6 13453 4 12 MASS ELEMENT DATA DATA-ERR 13453 4 13 NO-DIM NO-DIM NO-DIM NO-DIM 13453 4 14 97. 40. 2.82 2.7 13453 4 15 109. 46. 5.97 -03 1.8 13453 4 16 111. 47. 0.90 -03 2.4 13453 4 17 112. 46. 0.92 -03 0.9 13453 4 18 115. 48. 3.10 -03 1.8 13453 4 19 136. 55. 1.65 -04 1.1 13453 4 20 ENDDATA 8 13453 4 21 ENDSUBENT 4 13453 499999 ENDENTRY 3 1345399999999 ENTRY 13694 19980811 13694 0 1 SUBENT 13694001 19981019 13694 1 1 BIB 13 23 13694 1 2 INSTITUTE (1USALTI,1USALAS) 13694 1 3 REFERENCE (C,97TRIEST,2,1323,9705) 13694 1 4 AUTHOR (J.M.CAMPBELL,G.P.COUCHELL,S.LI,H.V.NGUYEN,D.J.PULLEN, 13694 1 5 E.H.SEABURY,W.A.SCHEIR,S.V.TIPNIS,T.R.ENGLAND) 13694 1 6 TITLE Yields of short-lived fission products following 238U 13694 1 7 fast fission 13694 1 8 FACILITY (REAC,1USALTI) UMASS Lowell research reactor. 13694 1 9 INC-SOURCE (REAC) Core of fast port in reactor. 13694 1 10 SAMPLE Depleted uranium foils lined in a cd-covered 13694 1 11 hemispherical fission chamber. 13694 1 12 METHOD (HEJET,FPGAM) Gamma-spectra measured at delay times 13694 1 13 from 0.3 to 4000 sec following rapid and uniform 13694 1 14 transfer of fission fragments with helium-jet/tape 13694 1 15 transport system. 13694 1 16 DETECTOR (GE-IN) HPGe detector. 13694 1 17 ANALYSIS Bateman equations were used to account for beta chain 13694 1 18 contributions to the yields. The beta-to-gamma 13694 1 19 ratios were taken from ENSDF except as noted under 13694 1 20 decay data. 13694 1 21 ERR-ANALYS (DATA-ERR) Source of uncertainties not given. 13694 1 22 STATUS Data taken from reference. 13694 1 23 No reply to author proof sent to J. Campbell. 13694 1 24 HISTORY (19980623C) 13694 1 25 ENDBIB 23 13694 1 26 COMMON 1 3 13694 1 27 EN-DUMMY 13694 1 28 MEV 13694 1 29 14. 13694 1 30 ENDCOMMON 1 3 13694 1 31 ENDSUBENT 1 13694 199999 SUBENT 13694002 19981019 13694 2 1 BIB 2 67 13694 2 2 REACTION (92-U-238(N,F)ELEM/MASS,IND,FY,,FST) 13694 2 3 DECAY-DATA ((1.)35-BR-89,4.4SEC,DG) 13694 2 4 ((2.)37-RB-89,15.MIN,DG) 13694 2 5 ((3.)35-BR-90,1.9SEC,DG) 13694 2 6 ((4.)37-RB-90-G,2.63MIN,DG) 13694 2 7 ((5.)37-RB-90-M,4.30MIN,DG) 13694 2 8 ((6.)37-RB-91,58.SEC,DG) 13694 2 9 ((7.)37-RB-92,4.5SEC,DG) 13694 2 10 ((8.)37-RB-93,5.8SEC,DG) 13694 2 11 ((9.)38-SR-93,7.4MIN,DG) 13694 2 12 ((10.)37-RB-94,2.7SEC,DG) 13694 2 13 ((11.)38-SR-94,75.3SEC,DG) 13694 2 14 ((12.)39-Y-94,19.MIN,DG) 13694 2 15 ((13.)37-RB-95,0.38SEC,DG) 13694 2 16 ((14.)38-SR-95,24.SEC,DG) 13694 2 17 ((15.)39-Y-95,10.MIN,DG) 13694 2 18 ((16.)37-RB-96,0.2SEC,DG) 13694 2 19 ((17.)38-SR-96,1.07SEC,DG) 13694 2 20 ((18.)39-Y-96-M,0.6SEC,DG) 13694 2 21 ((19.)38-SR-97,0.43SEC,DG) 13694 2 22 ((20.)39-Y-97-G,3.8SEC,DG) 13694 2 23 ((21.)39-Y-97-M,1.2SEC,DG) 13694 2 24 ((22.)38-SR-98,0.65SEC,DG) 13694 2 25 ((23.)39-Y-98-G,0.55SEC,DG) 13694 2 26 ((24.)38-SR-99,0.27SEC,DG) 13694 2 27 ((25.)39-Y-99,1.47SEC,DG) 13694 2 28 ((26.)40-ZR-99,2.1SEC,DG) 13694 2 29 ((27.)41-NB-99-M,2.6MIN,DG) 13694 2 30 ((28.)39-Y-100-G,0.74SEC,DG) 13694 2 31 Using gamma-to-beta ratios of Rudstam. 13694 2 32 ((29.)40-ZR-100,7.1SEC,DG) 13694 2 33 ((30.)41-NB-100-G,1.5SEC,DG) 13694 2 34 ((31.)41-NB-100-M,3.0SEC,DG) 13694 2 35 ((32.)40-ZR-102,2.9SEC,DG) 13694 2 36 ((33.)40-ZR-104,1.2SEC,DG) 13694 2 37 ((34.)42-MO-104,60.SEC,DG) 13694 2 38 ((35.)42-MO-105,36.SEC,DG) 13694 2 39 ((36.)51-SB-134-M,0.8SEC,DG) 13694 2 40 ((37.)52-TE-134,42.MIN,DG) 13694 2 41 ((38.)53-I-134-G,52.MIN,DG) 13694 2 42 ((39.)52-TE-135,19.SEC,DG) 13694 2 43 ((40.)52-TE-136,17.5SEC,DG) 13694 2 44 ((41.)53-I-136-G,83.SEC,DG) 13694 2 45 ((42.)53-I-136-M,47.SEC,DG) 13694 2 46 ((43.)52-TE-137,2.5SEC,DG) 13694 2 47 Using gamma-to-beta ratios of Rudstam. 13694 2 48 ((44.)53-I-138,6.5SEC,DG) 13694 2 49 ((45.)55-CS-140,64.SEC,DG) 13694 2 50 ((46.)55-CS-141,25.SEC,DG) 13694 2 51 ((47.)55-CS-142,1.7SEC,DG) 13694 2 52 ((48.)56-BA-142,11.MIN,DG) 13694 2 53 ((49.)55-CS-143,1.78SEC,DG) 13694 2 54 ((50.)56-BA-143,14.SEC,DG) 13694 2 55 ((51.)57-LA-143,14.MIN,DG) 13694 2 56 ((52.)55-CS-144,1.01SEC,DG) 13694 2 57 Using gamma-to-beta ratios of Rudstam. 13694 2 58 ((53.)56-BA-144,11.5SEC,DG) 13694 2 59 ((54.)57-LA-144,41.SEC,DG) 13694 2 60 ((55.)55-CS-145,0.60SEC,DG) 13694 2 61 ((56.)56-BA-145,4.3SEC,DG) 13694 2 62 ((57.)57-LA-145,25.SEC,DG) 13694 2 63 ((58.)56-BA-146,2.2SEC,DG) 13694 2 64 ((59.)57-LA-146-G,6.3SEC,DG) 13694 2 65 ((60.)58-CE-146,14.MIN,DG) 13694 2 66 ((61.)56-BA-147,0.89SEC,DG) 13694 2 67 ((62.)57-LA-147,4.0SEC,DG) 13694 2 68 ((63.)57-LA-148,1.43SEC,DG) 13694 2 69 ENDBIB 67 13694 2 70 NOCOMMON 0 0 13694 2 71 DATA 6 65 13694 2 72 MASS ELEMENT ISOMER DATA DATA-ERR DECAY-FLAG 13694 2 73 NO-DIM NO-DIM NO-DIM PC/FIS PC/FIS NO-DIM 13694 2 74 89. 35. 2.601 0.263 1. 13694 2 75 89. 37. 0.516 0.045 2. 13694 2 76 90. 35. 1.085 0.148 3. 13694 2 77 90. 37. 0. 0.295 0.075 4. 13694 2 78 90. 37. 1. 0.359 0.046 5. 13694 2 79 91. 37. 0.869 0.081 6. 13694 2 80 92. 37. 0.313 0.073 7. 13694 2 81 93. 37. 2.599 0.181 8. 13694 2 82 93. 38. 0.658 0.070 9. 13694 2 83 94. 37. 2.128 0.129 10. 13694 2 84 94. 38. 1.498 0.118 11. 13694 2 85 94. 39. 0.148 0.126 12. 13694 2 86 95. 37. 2.182 0.148 13. 13694 2 87 95. 38. 2.558 0.207 14. 13694 2 88 95. 39. 0.725 0.587 15. 13694 2 89 96. 37. 0.767 0.072 16. 13694 2 90 96. 38. 2.619 0.181 17. 13694 2 91 96. 39. 1. 0.443 0.031 18. 13694 2 92 97. 38. 2.892 0.194 19. 13694 2 93 97. 39. 0. 0.650 0.193 20. 13694 2 94 97. 39. 1. 0.975 0.098 21. 13694 2 95 97. 39. 1.625 0.291 13694 2 96 98. 38. 1.852 0.146 22. 13694 2 97 98. 39. 0. 2.832 0.196 23. 13694 2 98 99. 38. 1.157 0.111 24. 13694 2 99 99. 39. 2.124 0.190 25. 13694 2 100 99. 40. 1.260 0.131 26. 13694 2 101 99. 41. 1. 3.657 2.000 27. 13694 2 102 100. 39. 0. 1.330 0.109 28. 13694 2 103 100. 40. 4.034 0.432 29. 13694 2 104 100. 41. 0. 1.065 0.190 30. 13694 2 105 100. 41. 1. 3.264 0.549 31. 13694 2 106 102. 40. 7.833 0.883 32. 13694 2 107 104. 40. 5.017 0.933 33. 13694 2 108 104. 42. 0.990 1.458 34. 13694 2 109 105. 42. 3.397 0.279 35. 13694 2 110 134. 51. 1. 0.981 0.064 36. 13694 2 111 134. 52. 3.038 0.251 37. 13694 2 112 134. 53. 0. 0.540 0.130 38. 13694 2 113 135. 52. 3.344 0.284 39. 13694 2 114 136. 52. 2.556 0.189 40. 13694 2 115 136. 53. 0. 0.101 0.171 41. 13694 2 116 136. 53. 1. 0.141 0.013 42. 13694 2 117 136. 53. 0.242 0.184 13694 2 118 137. 52. 0.960 0.071 43. 13694 2 119 138. 53. 1.312 0.172 44. 13694 2 120 140. 55. 0.945 0.070 45. 13694 2 121 141. 55. 3.134 0.265 46. 13694 2 122 142. 55. 2.410 0.178 47. 13694 2 123 142. 56. 0.807 0.081 48. 13694 2 124 143. 55. 3.415 0.267 49. 13694 2 125 143. 56. 1.200 0.275 50. 13694 2 126 143. 57. 1.813 0.377 51. 13694 2 127 144. 55. 1.402 0.103 52. 13694 2 128 144. 56. 3.433 0.609 53. 13694 2 129 144. 57. 0.172 0.276 54. 13694 2 130 145. 55. 0.692 0.075 55. 13694 2 131 145. 56. 3.847 0.404 56. 13694 2 132 145. 57. 1.387 0.443 57. 13694 2 133 146. 56. 1.564 0.205 58. 13694 2 134 146. 57. 1.442 0.131 59. 13694 2 135 146. 58. 0.310 0.155 60. 13694 2 136 147. 56. 1.321 0.126 61. 13694 2 137 147. 57. 1.644 0.200 62. 13694 2 138 148. 57. 0.815 0.061 63. 13694 2 139 ENDDATA 67 13694 2 140 ENDSUBENT 6 13694 299999 ENDENTRY 2 1369499999999 ENTRY 21412 801107 21412 0 1 SUBENT 21412001 800318 21412 1 1 BIB 13 25 21412 1 2 INSTITUTE (2ITYPAV) RADIO CHEMISTRY LAB. 21412 1 3 REFERENCE (J,JIN,31,3739,6912) 21412 1 4 AUTHOR (R.STELLA,L.G.MORETTO,V.MAXIA,M.DI CASA,V.CRESPI, 21412 1 5 M.A.ROLLIER) 21412 1 6 TITLE -MASS DISTRIBUTION IN THE FISSION OF NP-237 WITH 21412 1 7 EPI-CADMIUM NEUTRONS -. 21412 1 8 FACILITY (REAC ) TRIGA MARK II LENA REACTOR OF THE UNIVERSITY 21412 1 9 OF PAVIA. 21412 1 10 INC-SOURCE (REAC ) REACTOR NEUTRONS. 21412 1 11 INC-SPECT .THE REACTOR SPECTRUM HAS A THERMAL FLUX OF 1.0E+13 21412 1 12 N/SEC AND A CADMIUM RATIO FOR GOLD OF ABOUT 2. THE 21412 1 13 SAMPLE OF NP-237 WAS SHIELDED BY 2 MM CADMIUM TO 21412 1 14 ELIMINATE THERMAL CAPTURE. 21412 1 15 SAMPLE .NEPTUNIUM DIOXIDE FROM O.R.N.L. 10 MG NPO2 AND 0.6 MG 21412 1 16 OF 93 PERCENT ENRICHED URANIUM 235. FISSION PRODUCTS 21412 1 17 WERE CHEMICALLY SEPERATED BY PRECIPITATION AND 21412 1 18 SOLVENT EXTRACTION PROCEDURES BEFORE COUNTING. 21412 1 19 METHOD (ACTIV) MEASUREMENT OF RADIO-ACTIVE DECAY OF FISSION 21412 1 20 PRODUCTS. 21412 1 21 DETECTOR (NAICR) NAI(TL) CRYSTAL, 3 BY 3 INCH. 21412 1 22 ERR-ANALYS .UNCERTAINTIES ARE ONE STANDARD DEVIATION FROM 21412 1 23 AVERAGE OF SEVERAL INDEPENDANT MEASUREMENTS. 21412 1 24 STATUS .TABLES IN JIN,31,3739. 21412 1 25 HISTORY (800304C) 21412 1 26 (800318E) 21412 1 27 ENDBIB 25 21412 1 28 COMMON 1 3 21412 1 29 EN-MIN 21412 1 30 EV 21412 1 31 6.3000E-01 21412 1 32 ENDCOMMON 1 3 21412 1 33 ENDSUBENT 1 21412 199999 SUBENT 21412002 800318 21412 2 1 BIB 4 23 21412 2 2 REACTION (93-NP-237(N,F)ELEM/MASS,CUM,FY,,SPA) RELATIVE FISSION 21412 2 3 YIELDS IN THE EPICADMIUM FISSION OF NP-237. 21412 2 4 MONITOR (93-NP-237(N,F)57-LA-140,CUM,FY,,SPA) VALUE TAKEN 21412 2 5 AS 6.35 PC/FIS FOR NORMALISATION. 21412 2 6 DECAY-DATA (39-Y-93,10.00HR,DG) 21412 2 7 (40-ZR-95,65.00D,DG) 21412 2 8 (40-ZR-97,17.00HR,DG) 21412 2 9 (42-MO-99,66.00HR,DG) 21412 2 10 (47-AG-111,7.50D,DG) 21412 2 11 (48-CD-115,2.30D,DG) 21412 2 12 (53-I-131,8.06D,DG) 21412 2 13 (52-TE-132,78.00HR,DG) 21412 2 14 (53-I-133,20.80HR,DG) 21412 2 15 (54-XE-135,9.20HR,DG) 21412 2 16 (57-LA-140,40.00HR,DG,1600.) 21412 2 17 (58-CE-141,32.50D,DG) 21412 2 18 (58-CE-143,33.40HR,DG) 21412 2 19 (58-CE-144,284.00D,DG) 21412 2 20 (60-ND-147,11.10D,DG) 21412 2 21 (61-PM-149,53.00HR,DG) 21412 2 22 (61-PM-151,28.40HR,DG) 21412 2 23 (62-SM-153,47.00HR,DG) 21412 2 24 STATUS .TABLE 1. 21412 2 25 ENDBIB 23 21412 2 26 COMMON 1 3 21412 2 27 MONIT 21412 2 28 PC/FIS 21412 2 29 6.3500E+00 21412 2 30 ENDCOMMON 1 3 21412 2 31 DATA 4 17 21412 2 32 ELEMENT MASS DATA DATA-ERR 21412 2 33 NO-DIM NO-DIM PC/FIS PC/FIS 21412 2 34 3.9000E+01 9.3000E+01 5.7200E+00 8.0000E-02 21412 2 35 4.0000E+01 9.5000E+01 5.7000E+00 1.2000E-01 21412 2 36 4.0000E+01 9.7000E+01 6.0400E+00 1.1000E-01 21412 2 37 4.2000E+01 9.9000E+01 6.7800E+00 2.4000E-01 21412 2 38 4.7000E+01 1.1100E+02 1.2200E-01 7.0000E-03 21412 2 39 4.8000E+01 1.1500E+02 5.3000E-02 3.0000E-03 21412 2 40 5.2000E+01 1.3200E+02 6.7200E+00 2.2000E-01 21412 2 41 5.3000E+01 1.3100E+02 3.4700E+00 2.8000E-01 21412 2 42 5.3000E+01 1.3300E+02 6.4200E+00 5.8000E-01 21412 2 43 5.4000E+01 1.3500E+02 5.3500E+00 1.3000E-01 21412 2 44 5.8000E+01 1.4100E+02 6.6700E+00 1.1000E-01 21412 2 45 5.8000E+01 1.4300E+02 5.5400E+00 1.2000E-01 21412 2 46 5.8000E+01 1.4400E+02 5.0700E+00 1.7000E-01 21412 2 47 6.0000E+01 1.4700E+02 3.2100E+00 1.5000E-01 21412 2 48 6.1000E+01 1.4900E+02 1.8800E+00 1.4000E-01 21412 2 49 6.1000E+01 1.5100E+02 1.0700E+00 5.0000E-02 21412 2 50 6.2000E+01 1.5300E+02 4.4000E-01 7.0000E-02 21412 2 51 ENDDATA 19 21412 2 52 ENDSUBENT 4 21412 299999 SUBENT 21412003 801107 21412 3 1 BIB 4 9 21412 3 2 REACTION (93-NP-237(N,F)ELEM/MASS,CUM,FY,,SPA) 21412 3 3 ANALYSIS .RELATIVE YIELDS IN TABLE 1 WERE CONVERTED TO ABSOLUTE 21412 3 4 VALUES BY NORMALIZING THE AREA UNDER THE FISSION YIELD21412 3 5 CURVE TO 200 PERCENT. 21412 3 6 MONITOR (92-U-235(N,F)56-BA-140,CUM,FY) VALUE TAKEN 21412 3 7 AS 5.60 PC/FIS, AND ASSUMED TO BE THE SAME FOR BOTH 21412 3 8 U-235 THERMAL FISSION AND NP-237 EPI-CADMIUM FISSION. 21412 3 9 STATUS .TABLE 2. 21412 3 10 (DEP,21412002) 21412 3 11 ENDBIB 9 21412 3 12 COMMON 1 3 21412 3 13 MONIT 21412 3 14 PC/FIS 21412 3 15 5.6000E+00 21412 3 16 ENDCOMMON 1 3 21412 3 17 DATA 4 17 21412 3 18 ELEMENT MASS DATA DATA-ERR 21412 3 19 NO-DIM NO-DIM PC/FIS PC/FIS 21412 3 20 3.9000E+01 9.3000E+01 5.1500E+00 7.0000E-02 21412 3 21 4.0000E+01 9.5000E+01 5.1300E+00 1.0000E-01 21412 3 22 4.0000E+01 9.7000E+01 5.4400E+00 1.0000E-01 21412 3 23 4.2000E+01 9.9000E+01 6.1100E+00 2.1000E-01 21412 3 24 4.7000E+01 1.1100E+02 1.1000E-01 6.0000E-03 21412 3 25 4.8000E+01 1.1500E+02 4.5000E-02 3.0000E-03 21412 3 26 5.2000E+01 1.3200E+02 5.9200E+00 1.9000E-01 21412 3 27 5.3000E+01 1.3100E+02 3.0600E+00 2.5000E-01 21412 3 28 5.3000E+01 1.3300E+02 5.6600E+00 5.1000E-01 21412 3 29 5.4000E+01 1.3500E+02 4.7100E+00 1.1000E-01 21412 3 30 5.8000E+01 1.4100E+02 5.8800E+00 1.0000E-01 21412 3 31 5.8000E+01 1.4300E+02 4.8800E+00 1.1000E-01 21412 3 32 5.8000E+01 1.4400E+02 4.4700E+00 1.5000E-01 21412 3 33 6.0000E+01 1.4700E+02 2.8300E+00 1.3000E-01 21412 3 34 6.1000E+01 1.4900E+02 1.6600E+00 1.2000E-01 21412 3 35 6.1000E+01 1.5100E+02 9.4000E-01 4.0000E-02 21412 3 36 6.2000E+01 1.5300E+02 3.9000E-01 4.0000E-02 21412 3 37 ENDDATA 19 21412 3 38 ENDSUBENT 4 21412 399999 ENDENTRY 3 2141299999999 ENTRY 21554 810404 21554 0 1 SUBENT 21554001 800612 21554 1 1 BIB 14 35 21554 1 2 INSTITUTE (2SWTWUR) WUERENLINGEN. 21554 1 3 REFERENCE (J,JIN,38,351,76) 21554 1 4 (P,INDC(SEC)-43,,7412) TO BE COMPLETED. 21554 1 5 (P,NEANDC(OR)-140,,7406) SUPERSEDED. 21554 1 6 AUTHOR (M.RAJAGOPALAN,H.S.PRUYS,A.GRUETTER,E.A.HERMES, 21554 1 7 H.R.VON GUNTEN) 21554 1 8 TITLE -MASS YIELDS IN THE 14 MEV NEUTRON INDUCED FISSION 21554 1 9 OF U-238 -. 21554 1 10 FACILITY (VDG ) VAN DER GRAAFF, NO DETAILS. 21554 1 11 INC-SOURCE (D-T ) DEUTERON BEAM ON TRITIUM TARGET, 14 MEV NEUTRO 21554 1 12 FLUX ABOUT 10*9 N/CM*2/SEC. 21554 1 13 (REAC ) THERMAL NEUTRONS FROM DORIT REACTOR, FLUX 21554 1 14 ABOUT 10*9 N/CM*2/SEC. 21554 1 15 SAMPLE .ONE GRAM SAMPLES OF NATURAL U3O8 AND 40 MG SAMPLES 21554 1 16 OF UO2 ENRICHED TO 97.5 PC IN U-235 WERE IRRADIATED 21554 1 17 WITH 14 MEV NEUTRONS AND THERMAL NEUTRONS. 21554 1 18 METHOD (ACTIV) MEASUREMENT OF GAMMA ACTIVITY OF UNSEPERATED 21554 1 19 FISSION PRODUCTS. 21554 1 20 DETECTOR (GELI ) HIGH RESOLUTION GE(LI) DETECTOR, RESOLUTION 21554 1 21 OF 2 KEV AT 1.3 MEV, FOR DETAILS SEE ARTICLE IN 21554 1 22 NSE,1977. 21554 1 23 MONITOR (92-U-238(N,F)56-BA-140,IND,FY) VALUE TAKEN 21554 1 24 AS 4.6 PC/FIS FOR 14 MEV NEUTRON INDUCED FISSION. 21554 1 25 CORRECTION .A SELF ABSORPTION CORRECTION WAS MADE FOR THICK 21554 1 26 UNSEPERATED SAMPLES. 21554 1 27 ERR-ANALYS .ONE STANDARD DEVIATION, INCLUDING THE STATISTICAL 21554 1 28 UNCERTAINTY, ABSORPTION CORRECTION, AND NORMALISATION 21554 1 29 UNCERATAINTIES. FOR THE ABSOLUTE DATA ON AG AND CD 21554 1 30 ISOTOPES THE ERROR INCLUDES UNCERTAINTIES IN THE 21554 1 31 DETECTOR CALIBRATION AND DECAY SCHEMES. OTHER 21554 1 32 SYSTEMATIC ERRORS WERE CONSIDERED TO BE LESS THAN 21554 1 33 FIVE PERCENT. 21554 1 34 STATUS .TABLE 1, JIN,38,351. 21554 1 35 HISTORY (800605C) 21554 1 36 (800612E) 21554 1 37 ENDBIB 35 21554 1 38 COMMON 1 3 21554 1 39 EN 21554 1 40 MEV 21554 1 41 1.4100E+01 21554 1 42 ENDCOMMON 1 3 21554 1 43 ENDSUBENT 1 21554 199999 SUBENT 21554002 810404 21554 2 1 BIB 5 38 21554 2 2 REACTION (92-U-238(N,F)ELEM/MASS,CUM,FY) CUMULATIVE FISSION 21554 2 3 YIELDS. 21554 2 4 DECAY-DATA ((1.)36-KR-85-M,4.48HR,DG) 21554 2 5 ((2.)36-KR-87,76.MIN,DG) 21554 2 6 ((3.)36-KR-88,2.84HR,DG) 21554 2 7 ((4.)38-SR-91,9.5HR,DG) 21554 2 8 ((5.)38-SR-92,2.72HR,DG) 21554 2 9 ((6.)39-Y-92,3.54HR,DG) 21554 2 10 ((7.)39-Y-93,10.2HR,DG) 21554 2 11 ((8.)40-ZR-95,64.0D,DG) 21554 2 12 ((9.)40-ZR-97,16.9HR,DG) 21554 2 13 ((10.)42-MO-99,66.02HR,DG) 21554 2 14 ((11.)43-TC-101,14.3MIN,DG) 21554 2 15 ((12.)44-RU-103,39.4D,DG) 21554 2 16 ((13.)44-RU-105,4.44HR,DG) 21554 2 17 ((14.)47-AG-111-G,7.45D,DG) 21554 2 18 ((15.)47-AG-112,3.14HR,DG) 21554 2 19 ((16.)47-AG-113,1.15MIN,DG) 21554 2 20 ((17.)48-CD-115,53.4HR,DG) 21554 2 21 ((18.)51-SB-129,4.4HR,DG) 21554 2 22 ((19.)52-TE-132,78.0HR,DG) 21554 2 23 ((20.)53-I-131,8.040D,DG) 21554 2 24 ((21.)53-I-133-G,20.9HR,DG) 21554 2 25 ((22.)53-I-134-G,52.6MIN,DG) 21554 2 26 ((23.)53-I-135,6.61HR,DG) 21554 2 27 ((24.)54-XE-135-G,9.10HR,DG) 21554 2 28 ((25.)55-CS-138-G,32.2MIN,DG) 21554 2 29 ((26.)56-BA-139,82.9MIN,DG) 21554 2 30 ((27.)57-LA-142,93.0MIN,DG) 21554 2 31 ((28.)58-CE-141,32.5D,DG) 21554 2 32 ((29.)58-CE-143,33.0HR,DG) 21554 2 33 ((30.)60-ND-147,11.0D,DG) 21554 2 34 ((31.)60-ND-149,1.73HR,DG) 21554 2 35 ((32.)61-PM-151,28.4HR,DG) 21554 2 36 DECAY-MON (56-BA-140,12.79D,DG) 21554 2 37 STATUS .TABLE 1. 21554 2 38 HISTORY (800605C) 21554 2 39 (800612E) 21554 2 40 ENDBIB 38 21554 2 41 COMMON 1 3 21554 2 42 MONIT 21554 2 43 PC/FIS 21554 2 44 4.6000E+00 21554 2 45 ENDCOMMON 1 3 21554 2 46 DATA 5 32 21554 2 47 ELEMENT MASS DATA DATA-ERR DECAY-FLAG 21554 2 48 NO-DIM NO-DIM PC/FIS PC/FIS NO-DIM 21554 2 49 3.6000E+01 8.5000E+01 1.4400E+00 3.0000E-01 1.0000E+00 21554 2 50 3.6000E+01 8.7000E+01 2.1300E+00 3.4000E-01 2.0000E+00 21554 2 51 3.6000E+01 8.8000E+01 2.7300E+00 1.8000E-01 3.0000E+00 21554 2 52 3.8000E+01 9.1000E+01 3.5900E+00 2.0000E-01 4.0000E+00 21554 2 53 3.8000E+01 9.2000E+01 3.8700E+00 2.6000E-01 5.0000E+00 21554 2 54 3.9000E+01 9.2000E+01 3.8500E+00 2.6000E-01 6.0000E+00 21554 2 55 3.9000E+01 9.3000E+01 4.3600E+00 3.5000E-01 7.0000E+00 21554 2 56 4.0000E+01 9.5000E+01 4.7200E+00 2.7000E-01 8.0000E+00 21554 2 57 4.0000E+01 9.7000E+01 4.9400E+00 3.2000E-01 9.0000E+00 21554 2 58 4.2000E+01 9.9000E+01 5.5500E+00 3.1000E-01 1.0000E+01 21554 2 59 4.3000E+01 1.0100E+02 4.9000E+00 3.5000E-01 1.1000E+01 21554 2 60 4.4000E+01 1.0300E+02 4.6900E+00 2.7000E-01 1.2000E+01 21554 2 61 4.4000E+01 1.0500E+02 3.4300E+00 5.9000E-01 1.3000E+01 21554 2 62 4.7000E+01 1.1100E+02 9.6000E-01 1.5000E-01 1.4000E+01 21554 2 63 4.7000E+01 1.1200E+02 9.9000E-01 1.5000E-01 1.5000E+01 21554 2 64 4.7000E+01 1.1300E+02 1.1600E+00 1.8000E-01 1.6000E+01 21554 2 65 4.8000E+01 1.1500E+02 9.7000E-01 1.5000E-01 1.7000E+01 21554 2 66 5.1000E+01 1.2900E+02 1.5600E+00 1.3000E-01 1.8000E+01 21554 2 67 5.2000E+01 1.3200E+02 4.3100E+00 2.4000E-01 1.9000E+01 21554 2 68 5.3000E+01 1.3100E+02 3.7500E+00 2.2000E-01 2.0000E+01 21554 2 69 5.3000E+01 1.3300E+02 5.7300E+00 3.7000E-01 2.1000E+01 21554 2 70 5.3000E+01 1.3400E+02 5.4900E+00 4.5000E-01 2.2000E+01 21554 2 71 5.3000E+01 1.3500E+02 5.4400E+00 3.2000E-01 2.3000E+01 21554 2 72 5.4000E+01 1.3500E+02 6.1900E+00 3.5000E-01 2.4000E+01 21554 2 73 5.5000E+01 1.3800E+02 5.1000E+00 8.0000E-01 2.5000E+01 21554 2 74 5.6000E+01 1.3900E+02 5.1000E+00 3.2000E-01 2.6000E+01 21554 2 75 5.7000E+01 1.4200E+02 3.8700E+00 2.1000E-01 2.7000E+01 21554 2 76 5.8000E+01 1.4100E+02 4.0400E+00 2.2000E-01 2.8000E+01 21554 2 77 5.8000E+01 1.4300E+02 3.6200E+00 1.9000E-01 2.9000E+01 21554 2 78 6.0000E+01 1.4700E+02 2.0100E+00 1.4000E-01 3.0000E+01 21554 2 79 6.0000E+01 1.4900E+02 1.3600E+00 1.2000E-01 3.1000E+01 21554 2 80 6.1000E+01 1.5100E+02 7.9000E-01 5.0000E-02 3.2000E+01 21554 2 81 ENDDATA 34 21554 2 82 ENDSUBENT 5 21554 299999 ENDENTRY 2 2155499999999 ENTRY 21561 810404 21561 0 1 SUBENT 21561001 800612 21561 1 1 BIB 13 26 21561 1 2 INSTITUTE (2FR GRE) LAB. DE CHIMIE NUCLEAIRE. 21561 1 3 REFERENCE (J,JRC,7,309,71) 21561 1 4 (P,NEANDC(E)-161U,,76) ABST. 21561 1 5 AUTHOR (J.BLACHOT,L.C.CARRAZ,P.CAVALLINI,E.MONNAND, 21561 1 6 F.SCHUSSLER) 21561 1 7 TITLE -DIRECT GAMMA SPECTROSCOPY ANALYSIS OF FISSION 21561 1 8 PRODUCTS FROM U-235, APPLICATION TO THE MASS 21561 1 9 DISTRIBUTION OF FISSION PRODUCTS FROM FISSION 21561 1 10 OF TH-232 BY 14 MEV NEUTRONS -. 21561 1 11 FACILITY .SAMES ACCELERATOR, 300KV. 21561 1 12 INC-SOURCE (D-T ) 300 KEV DEUTERIUM BEAM ON TRITIUM TARGET. 21561 1 13 NEUTRON FLUX ABOUT 10*11 N/CM*2/SEC. 21561 1 14 SAMPLE .NO DETAILS, TH-232. 21561 1 15 METHOD (ACTIV) MEASUREMENT OF GAMMA ACTIVITIES IN 21561 1 16 UNSEPERATED FISSION PRODUCTS AT 3, 7 AND 110 21561 1 17 HOURS AFTER A 15 MINUTE IRRADIATION. 21561 1 18 DETECTOR (GELI ) 40 CM*3 COAXIAL GE(LI) DETECTOR, WITH 21561 1 19 RESOLUTION OF 4 KEV AT 1.3 MEV. 21561 1 20 MONITOR (92-U-235(N,F)57-LA-140,CUM,FY,,MXW) MEASUREMENTS 21561 1 21 ARE NORMALISED TO THERMAL U-235 YIELDS TAKEN FROM 21561 1 22 WAHL,IAEA SM-122/116,831,1969. A VALUE OF 6.43 21561 1 23 FOR THE YIELD OF LA-140 IS GIVEN FOR REFERENCE. 21561 1 24 ERR-ANALYS .NO ERRORS GIVEN. 21561 1 25 STATUS .TABLE 4, JRC,7,309. 21561 1 26 HISTORY (800606C) 21561 1 27 (800612E) 21561 1 28 ENDBIB 26 21561 1 29 COMMON 2 3 21561 1 30 EN MONIT 21561 1 31 MEV PC/FIS 21561 1 32 1.4100E+01 6.4300E+00 21561 1 33 ENDCOMMON 2 3 21561 1 34 ENDSUBENT 2 21561 199999 SUBENT 21561002 810404 21561 2 1 BIB 4 17 21561 2 2 REACTION (90-TH-232(N,F)ELEM/MASS,CUM,FY) 21561 2 3 CUMULATIVE FISSION YIELDS FOR 14 MEV NEUTRON 21561 2 4 INDUCED FISSION. 21561 2 5 DECAY-DATA ((1.)36-KR-88,2.8HR,DG,1529.,,DG,2392.) 21561 2 6 ((2.)38-SR-91,9.7HR,DG,555.6,,DG,1024.3) 21561 2 7 ((3.)39-Y-92,3.5HR,DG,934.6,,DG,1405.) 21561 2 8 ((4.)39-Y-93,10.2HR,DG,267.,,DG,1918.) 21561 2 9 ((5.)41-NB-97,72.MIN,DG,658.1) 21561 2 10 ((6.)53-I-132,2.3HR,DG,772.9) 21561 2 11 ((7.)53-I-133,21.HR,DG,529.9,,DG,1236.) 21561 2 12 ((8.)53-I-134,53.MIN,DG,847.,,DG,1073.) 21561 2 13 ((9.)53-I-135,6.7HR,DG,1260.4,,DG,1678.5) 21561 2 14 ((10.)55-CS-138,32.MIN,DG,1438.,,DG,1010.) 21561 2 15 ((11.)57-LA-142,85.MIN,DG,640.9,,DG,2543.) 21561 2 16 STATUS .TABLE 4. 21561 2 17 HISTORY (800606C) 21561 2 18 (800612E) 21561 2 19 ENDBIB 17 21561 2 20 NOCOMMON 0 0 21561 2 21 DATA 4 11 21561 2 22 ELEMENT MASS DATA DECAY-FLAG 21561 2 23 NO-DIM NO-DIM PC/FIS NO-DIM 21561 2 24 3.6000E+01 8.8000E+01 4.9700E+00 1.0000E+00 21561 2 25 3.8000E+01 9.1000E+01 5.9000E+00 2.0000E+00 21561 2 26 3.9000E+01 9.2000E+01 5.8300E+00 3.0000E+00 21561 2 27 3.9000E+01 9.3000E+01 6.4000E+00 4.0000E+00 21561 2 28 4.1000E+01 9.7000E+01 3.4800E+00 5.0000E+00 21561 2 29 5.3000E+01 1.3200E+02 5.8400E+00 6.0000E+00 21561 2 30 5.3000E+01 1.3300E+02 5.2800E+00 7.0000E+00 21561 2 31 5.3000E+01 1.3400E+02 4.8600E+00 8.0000E+00 21561 2 32 5.3000E+01 1.3500E+02 5.9600E+00 9.0000E+00 21561 2 33 5.5000E+01 1.3800E+02 7.4000E+00 1.0000E+01 21561 2 34 5.7000E+01 1.4200E+02 5.3400E+00 1.1000E+01 21561 2 35 ENDDATA 13 21561 2 36 ENDSUBENT 4 21561 299999 ENDENTRY 2 2156199999999 ENTRY 21567 810404 21567 0 1 SUBENT 21567001 810404 21567 1 1 BIB 13 49 21567 1 2 INSTITUTE (2FR GRE) 21567 1 3 REFERENCE (T,FEU ALVIM,750612) FRNC-TH-584. 21567 1 4 (J,JPR,38,,273,7703) 21567 1 5 (J,CEC,29,7,347,7706) ABSTRACT 21567 1 6 (R,CEA-N-1817,1,75) KR,XE YIELDS. 21567 1 7 AUTHOR (C.FEU ALVIM) 21567 1 8 TITLE -MEASUREMENT OF THE MASS AND CHARGE DISTRIBUTIONS 21567 1 9 IN NEUTRON INDUCED FISSION AT MEDIUM ENERGY BY 21567 1 10 AN EMANATION METHOD.-(IN FRENCH).- 21567 1 11 FACILITY .300 KEV DEUTERON ACCELERATOR S.A.M.E.S. 21567 1 12 INC-SOURCE (D-T ) DEUTERON-TRITIUM REACTION. 300 KEV 21567 1 13 DEUTERONS ONTO TRITIATED TARGET OF 30 MM DIAM. 21567 1 14 SAMPLE .URANYLSTEARATE OR THORIUM STEARATE. EMANATION 21567 1 15 TESTS WERE DONE ON EACH SAMPLE. 21567 1 16 METHOD (CHSEP) CHEMICAL SEPARATION. RARE GASES ARE 21567 1 17 EXTRACTED FROM THE FISSION TARGET BY PUMPING 21567 1 18 IN VACUUM AFTER OR DURING IRRADIATION. IN 21567 1 19 SOME CASES THE IRRADIATED MATERIAL WAS PASSED 21567 1 20 OVER A RESIN AS TO REDUCE COMPTON BACKGROUND 21567 1 21 AND PEAK INTERFERENCES IN THEIR GAMMA-COUNTING. 21567 1 22 USING THE FORMULAS - 21567 1 23 F = (Y-CUM(ELEM) - Y-CUM(RARE GAS))/ 21567 1 24 (Y-CUM(ELEM) AND 21567 1 25 F = N1*N4/(N2*N3) WHERE 21567 1 26 N1= COUNTING RATE DURING IRRADIATION, 21567 1 27 N2= COUNTING RATE AFTER IRRADIATION, 21567 1 28 N3= COUNTING RATE DURING IRRADIATION FOR 21567 1 29 A REFERENCE MATERIAL. 21567 1 30 N4= COUNTING RATE AFTER IRRADIATION FOR 21567 1 31 A REFERENCE MATERIAL. 21567 1 32 FRACTIONAL YIELDS CAN BE DERIVED. 21567 1 33 DETECTOR (GELI ) COAXIAL GE(LI)-DETECTOR FROM COMPANY 21567 1 34 QUARTZ ET SILICE, 43 CC, FWHM-RESOL AT THE 21567 1 35 1332 KEV-LINE OF CO-60 IS 2.35 KEV, PEAK/COMPTON 21567 1 36 RATIO 26., EFFICIENCY WITH RESPECT TO A NA-I 21567 1 37 OF 76*76 MM*MM AT 25 CM FROM SOURCE IS 7. PERC. 21567 1 38 (GELI ) 52 CC GE(LI) DETECTOR FROM COMPANY 21567 1 39 SCHLUMBERGER, RESOLUTION LESS THAN 2.1 KEV, 21567 1 40 P/C RATIO BETTER THAN 32. 21567 1 41 ERR-ANALYS .QUADRATIC ERROR PROPAGATION USED IN THE 21567 1 42 FORMULA F=N1*N4/(N2*N3). 21567 1 43 COMMENT .DECAY DATA FROM J.BLACHOT AND C.FICHE, 21567 1 44 BIBLIOTHEQUE DES DONNEES NUCLEAIRES SUR LES 21567 1 45 PRODUITS DE FISSION, EDITION OF 20.01.75, 21567 1 46 CEA-NOTE TO BE PUBLISHED IN 1975. 21567 1 47 .TWO OTHER EXPERIMENTAL METHODS ARE DESCRIBED. 21567 1 48 STATUS .TEXT, THESIS. 21567 1 49 HISTORY (800606C) G.C. 21567 1 50 (800612E) 21567 1 51 ENDBIB 49 21567 1 52 COMMON 2 3 21567 1 53 EN EN-RSL 21567 1 54 MEV MEV 21567 1 55 1.4700E+01 5.0000E-01 21567 1 56 ENDCOMMON 2 3 21567 1 57 ENDSUBENT 2 21567 199999 SUBENT 21567002 800612 21567 2 1 BIB 3 6 21567 2 2 REACTION ((92-U-238(N,F)ELEM/MASS,CUM,FY)/ 21567 2 3 (92-U-238(N,F)MASS,CHN,FY)) FRACTIONAL 21567 2 4 CUMULATIVE YIELDS. 21567 2 5 STATUS .TABLE 8-1, P.64, THESIS. 21567 2 6 HISTORY (800606C) G.C. 21567 2 7 (800612E) 21567 2 8 ENDBIB 6 21567 2 9 NOCOMMON 0 0 21567 2 10 DATA 4 10 21567 2 11 ELEMENT MASS RATIO RATIO-ERR 21567 2 12 NO-DIM NO-DIM NO-DIM NO-DIM 21567 2 13 3.6000E+01 8.9000E+01 9.7000E-01 1.0000E-02 21567 2 14 3.6000E+01 9.1000E+01 6.4300E-01 7.0000E-03 21567 2 15 3.6000E+01 9.2000E+01 4.4400E-01 6.0000E-03 21567 2 16 3.6000E+01 9.3000E+01 1.5800E-01 2.0000E-02 21567 2 17 3.6000E+01 9.5000E+01 1.5000E-02 2.0000E-02 21567 2 18 5.4000E+01 1.3800E+02 8.4200E-01 2.0000E-03 21567 2 19 5.4000E+01 1.3900E+02 7.0900E-01 7.0000E-03 21567 2 20 5.4000E+01 1.4000E+02 6.1600E-01 5.0000E-03 21567 2 21 5.4000E+01 1.4100E+02 3.0500E-01 1.4000E-02 21567 2 22 5.4000E+01 1.4200E+02 1.1200E-01 1.1000E-02 21567 2 23 ENDDATA 12 21567 2 24 ENDSUBENT 4 21567 299999 SUBENT 21567003 800612 21567 3 1 BIB 3 6 21567 3 2 REACTION ((90-TH-232(N,F)ELEM/MASS,CUM,FY)/ 21567 3 3 (90-TH-232(N,F)MASS,CHN,FY)) FRACTIONAL 21567 3 4 CUMULATIVE YIELDS. 21567 3 5 STATUS .TABLE 8-2, P.65, THESIS. 21567 3 6 HISTORY (800606C) G.C. 21567 3 7 (800612E) 21567 3 8 ENDBIB 6 21567 3 9 NOCOMMON 0 0 21567 3 10 DATA 4 10 21567 3 11 ELEMENT MASS RATIO RATIO-ERR 21567 3 12 NO-DIM NO-DIM NO-DIM NO-DIM 21567 3 13 3.6000E+01 8.9000E+01 9.5500E-01 2.0000E-02 21567 3 14 3.6000E+01 9.1000E+01 6.2000E-01 2.0000E-02 21567 3 15 3.6000E+01 9.2000E+01 3.8000E-01 2.0000E-02 21567 3 16 3.6000E+01 9.3000E+01 2.0000E-01 3.0000E-02 21567 3 17 3.6000E+01 9.4000E+01 7.0000E-02 7.0000E-02 21567 3 18 5.4000E+01 1.3800E+02 9.0900E-01 9.0000E-03 21567 3 19 5.4000E+01 1.3900E+02 8.1500E-01 1.0000E-02 21567 3 20 5.4000E+01 1.4000E+02 6.1000E-01 7.0000E-02 21567 3 21 5.4000E+01 1.4100E+02 2.8000E-01 5.0000E-02 21567 3 22 5.4000E+01 1.4200E+02 1.0000E-01 2.0000E-02 21567 3 23 ENDDATA 12 21567 3 24 ENDSUBENT 4 21567 399999 ENDENTRY 3 2156799999999 ENTRY 21590 810617 21590 0 1 SUBENT 21590001 801124 21590 1 1 BIB 13 42 21590 1 2 INSTITUTE (2FR GRE) LAB. DE CHIMIE NUCLEAIRE. 21590 1 3 REFERENCE (J,JIN,36,495,74) 21590 1 4 AUTHOR (J.BLACHOT,L.C.CARRAZ,P.CAVALLINI,C.CHAUVIN,A.FERRIEU, 21590 1 5 A.MOUSSA) 21590 1 6 TITLE -MASS DISTRIBUTIONS IN FISSION OF U-238 BY 14 MEV 21590 1 7 NEUTRONS -. 21590 1 8 FACILITY (REAC ) THE MELUSINE REACTOR AT THE LABORATORY WAS 21590 1 9 USED FOR THE U-235 MEASUREMENT. 21590 1 10 .SAMES ACCELERATOR FOR THE U-238 MEASUREMENT. 21590 1 11 INC-SOURCE (REAC ) REACTOR NEUTRONS WITH A FAST TO THERMAL 21590 1 12 FLUX RATIO OF ABOUT 0.01 WAS USED FOR THE U-235 21590 1 13 MEASUREMENT. 21590 1 14 (D-T ) THE SAMES ACCELERATOR PRODUCED A 300 KEV 21590 1 15 DEUTERIUM BEAM ON A TRITIUM TARGET FOR THE U-238 21590 1 16 MEASUREMENTS. 21590 1 17 SAMPLE .URANYL NITRATE IN A SEALED POLYTHENE SACHET, ENRICHED 21590 1 18 TO 93 PERCENT U-235 FOR THERMAL FISSION MEASUREMENTS. 21590 1 19 .NATURAL URANIUM DIOXIDE IN A SEALED POLYTHENE SACHET 21590 1 20 FOR THE U-238 14 MEV MEASURMENTS. 21590 1 21 .FOR THE KRYPTON DATA URANYL STEARATE PREPARED BY THE 21590 1 22 TECHNIQUE OF WAHL WAS USED. 21590 1 23 METHOD (ACTIV) DECAY GAMMA MEASUREMENT AFTER CHEMICAL 21590 1 24 SEPERATION OF FISSION PRODUCTS. 21590 1 25 .THREE CHEMICALLY SEPERATED FRACTIONS WERE STUDIED, 21590 1 26 ALKALIS WITH ALKALI EARTHS AND RARE EARTHS, A FRACTIO 21590 1 27 WITH CADMIUM AND SILVER, AND A FRACTION WITH KRYPTON 21590 1 28 AND XENON, AND A FRACTION WITH IODINE. 21590 1 29 DETECTOR (GELI ) TWO COAXIAL GE(LI) DETECTORS, 43 AND 50 21590 1 30 CM*3, WITH RESOLUTION OF 2.3 AND 2.5 KEV AT 1.3 MEV. 21590 1 31 ANALYSIS .VALUES ARE WEIGHTED AVERAGES OF MANY INDEPENDANT 21590 1 32 MEASURMENTS. 21590 1 33 ERR-ANALYS .QUOTED UNCERTAINTY IS FROM A QUADRATIC COMBINATION 21590 1 34 OF ERRORS ON SEVERAL INDEPENDANT MEASURMENTS. THIS 21590 1 35 COMES FROM FOUR SOURCES, THE AREA OF GAMMA PEAKS, 21590 1 36 THE EFFICIENCY OF THE DETECTOR, THE UNCERTAINTY IN 21590 1 37 TIMING AND NUCLEAR DECAY DATA. 21590 1 38 STATUS .TABLES 2 AND 3, JIN,36,495. 21590 1 39 HISTORY (800610C) 21590 1 40 (800718E) 21590 1 41 (801106A) CHANGES IN MAIN BIB-SECTION AND DECAY-DATA 21590 1 42 IN SUBWORK 002. 21590 1 43 (801124E) 21590 1 44 ENDBIB 42 21590 1 45 NOCOMMON 0 0 21590 1 46 ENDSUBENT 0 21590 199999 SUBENT 21590003 810408 21590 3 1 BIB 5 8 21590 3 2 REACTION (92-U-238(N,F)ELEM/MASS,CUM,FY) 21590 3 3 MONITOR (92-U-238(N,F)36-KR-87,CUM,FY) VALUE TAKEN 21590 3 4 AS 1.63 PC/FIS. 21590 3 5 DECAY-DATA ((1.)36-KR-85-M,4.30HR,DG,151.0,0.74,DG,305.,0.133) 21590 3 6 ((2.)36-KR-88,2.80HR,DG,196.1,0.273,DG,834.7,0.103) 21590 3 7 STATUS .TABLE 3. 21590 3 8 HISTORY (800611C) 21590 3 9 (800718E) 21590 3 10 ENDBIB 8 21590 3 11 COMMON 2 3 21590 3 12 EN MONIT 21590 3 13 MEV PC/FIS 21590 3 14 1.4100E+01 1.6300E+00 21590 3 15 ENDCOMMON 2 3 21590 3 16 DATA 5 2 21590 3 17 ELEMENT MASS DATA DATA-ERR DECAY-FLAG 21590 3 18 NO-DIM NO-DIM PC/FIS PC/FIS NO-DIM 21590 3 19 3.6000E+01 8.5000E+01 9.8000E-01 7.0000E-02 1.0000E+00 21590 3 20 3.6000E+01 8.8000E+01 1.9500E+00 1.5000E-01 2.0000E+00 21590 3 21 ENDDATA 4 21590 3 22 ENDSUBENT 5 21590 399999 SUBENT 21590004 810408 21590 4 1 BIB 6 32 21590 4 2 REACTION (92-U-238(N,F)ELEM/MASS,CUM,FY) 21590 4 3 MONITOR (92-U-238(N,F)56-BA-140,CUM,FY) VALUE TAKEN 21590 4 4 AS 4.60 PC/FIS. 21590 4 5 DECAY-DATA ((1.)38-SR-91,9.72HR,DG,749.8,0.245,DG,1024.3,0.34) 21590 4 6 ((2.)38-SR-92,2.70HR,DG,241.5,0.0357,DG,1383.9,0.90) 21590 4 7 ((3.)39-Y-91-M,50.0MIN,DG,555.6,0.56) 21590 4 8 ((4.)39-Y-92,3.50HR,DG,934.5,0.14) 21590 4 9 ((5.)39-Y-93,10.19HR,DG,267.0,0.064,DG,947.0,0.022) 21590 4 10 ((6.)40-ZR-95,65.21D,DG,724.2,0.43,DG,756.7,0.546) 21590 4 11 ((7.)40-ZR-97,17.04HR,DG,743.0,0.94) 21590 4 12 ((8.)42-MO-99,2.79D,DG,180.9,0.058,DG,739.7,0.138) 21590 4 13 ((9.)44-RU-103,39.9D,DG,497.2,0.90) 21590 4 14 ((10.)44-RU-105,4.39HR,DG,469.4,0.175,DG,724.2,0.445) 21590 4 15 ((11.)45-RH-105,1.49D,DG,319.2,0.198) 21590 4 16 ((12.)47-AG-112,3.20HR,DG,616.8,0.435) 21590 4 17 ((13.)47-AG-113,5.30HR,DG,298.0,0.074) 21590 4 18 ((14.)48-CD-115-G,,DG) 21590 4 19 ((15.)48-CD-117,2.48HR,DG,273.3,0.17) 21590 4 20 ((16.)49-IN-115-M,4.39HR,DG,336.2,0.45) 21590 4 21 ((17.)51-SB-127,3.70D,DG,473.0,0.251,DG,685.7,0.368) 21590 4 22 ((18.)51-SB-129,4.30HR,DG,812.8,0.435) 21590 4 23 ((19.)52-TE-131-M1,25.D,DG,852.3,0.256) 21590 4 24 ((20.)57-LA-142,1.42HR,DG,641.2,0.465) 21590 4 25 ((21.)58-CE-141,32.47D,DG,145.4,0.493) 21590 4 26 ((22.)58-CE-143,1.38D,DG,293.3,0.465) 21590 4 27 ((23.)60-ND-147,11.08D,DG,531.0,0.131) 21590 4 28 ((24.)60-ND-149,1.70HR,DG,424.0,0.082,DG,541.0,0.066) 21590 4 29 ((25.)L1-PM-151,1.18D,DG,339.9,0.24) 21590 4 30 DECAY-MON (56-BA-140,13.0D,DG,162.7,0.061,DG,537.3,0.24) 21590 4 31 STATUS .TABLE 3. 21590 4 32 HISTORY (800611C) 21590 4 33 (800718E) 21590 4 34 ENDBIB 32 21590 4 35 COMMON 2 3 21590 4 36 EN MONIT 21590 4 37 MEV PC/FIS 21590 4 38 1.4100E+01 4.6000E+00 21590 4 39 ENDCOMMON 2 3 21590 4 40 DATA 5 26 21590 4 41 ELEMENT MASS DATA DATA-ERR DECAY-FLAG 21590 4 42 NO-DIM NO-DIM PC/FIS PC/FIS NO-DIM 21590 4 43 3.8000E+01 9.1000E+01 3.6400E+00 2.7000E-01 1.0000E+00 21590 4 44 3.8000E+01 9.2000E+01 3.9500E+00 4.0000E-01 2.0000E+00 21590 4 45 3.9000E+01 9.1000E+01 3.6000E+00 2.3000E-01 3.0000E+00 21590 4 46 3.9000E+01 9.2000E+01 3.8200E+00 2.9000E-01 4.0000E+00 21590 4 47 3.9000E+01 9.3000E+01 4.4800E+00 3.9000E-01 5.0000E+00 21590 4 48 4.0000E+01 9.5000E+01 4.7200E+00 3.6000E-01 6.0000E+00 21590 4 49 4.0000E+01 9.7000E+01 5.0500E+00 4.8000E-01 7.0000E+00 21590 4 50 4.1000E+01 9.7000E+01 4.7900E+00 4.4000E-01 21590 4 51 4.2000E+01 9.9000E+01 4.9600E+00 5.0000E-01 8.0000E+00 21590 4 52 4.4000E+01 1.0300E+02 4.5400E+00 3.4000E-01 9.0000E+00 21590 4 53 4.4000E+01 1.0500E+02 3.5700E+00 3.2000E-01 1.0000E+01 21590 4 54 4.5000E+01 1.0500E+02 3.2100E+00 3.8000E-01 1.1000E+01 21590 4 55 4.7000E+01 1.1200E+02 1.0300E+00 8.0000E-02 1.2000E+01 21590 4 56 4.7000E+01 1.1300E+02 9.7000E-01 1.0000E-01 1.3000E+01 21590 4 57 4.8000E+01 1.1500E+02 9.8000E-01 9.0000E-02 1.4000E+01 21590 4 58 4.8000E+01 1.1700E+02 4.7000E-01 5.0000E-02 1.5000E+01 21590 4 59 4.9000E+01 1.1500E+02 9.5000E-01 9.0000E-02 1.6000E+01 21590 4 60 5.1000E+01 1.2700E+02 1.4600E+00 1.6000E-01 1.7000E+01 21590 4 61 5.1000E+01 1.2900E+02 1.8700E+00 1.5000E-01 1.8000E+01 21590 4 62 5.2000E+01 1.3100E+02 6.0000E-01 6.0000E-02 1.9000E+01 21590 4 63 5.7000E+01 1.4200E+02 4.4500E+00 4.0000E-01 2.0000E+01 21590 4 64 5.8000E+01 1.4100E+02 4.5300E+00 6.4000E-01 2.1000E+01 21590 4 65 5.8000E+01 1.4300E+02 3.8300E+00 2.8000E-01 2.2000E+01 21590 4 66 6.0000E+01 1.4700E+02 2.1100E+00 1.6000E-01 2.3000E+01 21590 4 67 6.0000E+01 1.4900E+02 1.3700E+00 1.8000E-01 2.4000E+01 21590 4 68 6.1000E+01 1.5100E+02 6.8000E-01 7.0000E-02 2.5000E+01 21590 4 69 ENDDATA 28 21590 4 70 ENDSUBENT 5 21590 499999 SUBENT 21590005 810408 21590 5 1 BIB 6 10 21590 5 2 REACTION (92-U-238(N,F)ELEM/MASS,CUM,FY) 21590 5 3 MONITOR (92-U-238(N,F)53-I-131,CUM,FY) VALUE TAKEN 21590 5 4 AS 3.85 PC/FIS. 21590 5 5 DECAY-DATA ((1.)53-I-132,2.28HR,DG,667.7,0.98,DG,772.7,0.75) 21590 5 6 ((2.)53-I-133,20.99HR,DG,529.9,0.89,DG,875.5,0.044) 21590 5 7 ((3.)53-I-135,6.71HR,DG,1131.0,0.221,DG,1260.5,0.292) 21590 5 8 DECAY-MON (53-I-131,8.06D,DG,364.4,0.825,DG,637.0,0.067) 21590 5 9 STATUS .TABLE 3. 21590 5 10 HISTORY (800611C) 21590 5 11 (800718E) 21590 5 12 ENDBIB 10 21590 5 13 COMMON 2 3 21590 5 14 EN MONIT 21590 5 15 MEV PC/FIS 21590 5 16 1.4100E+01 3.8500E+00 21590 5 17 ENDCOMMON 2 3 21590 5 18 DATA 5 3 21590 5 19 ELEMENT MASS DATA DATA-ERR DECAY-FLAG 21590 5 20 NO-DIM NO-DIM PC/FIS PC/FIS NO-DIM 21590 5 21 5.3000E+01 1.3200E+02 4.9700E+00 3.5000E-01 2.0000E+00 21590 5 22 5.3000E+01 1.3300E+02 6.0000E+00 2.1000E-01 3.0000E+00 21590 5 23 5.3000E+01 1.3500E+02 4.9000E+00 3.0000E-01 4.0000E+00 21590 5 24 ENDDATA 5 21590 5 25 ENDSUBENT 5 21590 599999 ENDENTRY 4 2159099999999 ENTRY 21591 810408 21591 0 1 SUBENT 21591001 800718 21591 1 1 BIB 12 16 21591 1 2 INSTITUTE (2FR GRE) 21591 1 3 REFERENCE (P,CEA-N-1784,2,74) 21591 1 4 AUTHOR (C.FEU ALVIM DA SILVA,J.CRANCON) 21591 1 5 TITLE -MEASUREMENT OF SOME FRACTIONAL CUMULATIVE YIELDS IN 21591 1 6 THE 14 MEV FISSION OF U-238 -. 21591 1 7 FACILITY .SAMES ACCELERATOR. 21591 1 8 INC-SOURCE (D-T ) 300 KEV DEUTERON BEAM ON TRITIUM TARGET. 21591 1 9 SAMPLE .NATURAL URANIUM DIOXIDE. 21591 1 10 METHOD .METHOD OF WOLSBERG, USING THE HIGH SORPTION POWER 21591 1 11 OF BARIUM STEARATE FOR RARE GASES FOR SEPERATION 21591 1 12 OF FISSION PRODUCTS FOLLOWED BY GAMMA SPECTROSCOPY. 21591 1 13 DETECTOR (GELI ) GE(LI) NO DETAILS. 21591 1 14 ERR-ANALYS .ONE STANDARD DEVIATION, NO DETAILS. 21591 1 15 STATUS .TABLE ON PAGE 2, CEA-N-1784. 21591 1 16 HISTORY (800612C) 21591 1 17 (800718E) 21591 1 18 ENDBIB 16 21591 1 19 COMMON 1 3 21591 1 20 EN 21591 1 21 MEV 21591 1 22 1.4100E+01 21591 1 23 ENDCOMMON 1 3 21591 1 24 ENDSUBENT 1 21591 199999 SUBENT 21591002 810408 21591 2 1 BIB 4 7 21591 2 2 REACTION ((92-U-238(N,F)ELEM/MASS,CUM,FY)/ 21591 2 3 (92-U-238(N,F)MASS,CHN,FY)) 21591 2 4 FRACTIONAL CUMULATIVE FISSION YIELDS. 21591 2 5 PART-DET (DG ) DECAY GAMMAS, NO DETAILS. 21591 2 6 STATUS .TABLE ON PAGE 2. 21591 2 7 HISTORY (800612C) 21591 2 8 (800718E) 21591 2 9 ENDBIB 7 21591 2 10 NOCOMMON 0 0 21591 2 11 DATA 4 9 21591 2 12 ELEMENT MASS DATA DATA-ERR 21591 2 13 NO-DIM NO-DIM NO-DIM NO-DIM 21591 2 14 3.8000E+01 9.1000E+01 6.4300E-01 7.0000E-03 21591 2 15 3.8000E+01 9.2000E+01 4.4400E-01 6.0000E-03 21591 2 16 3.9000E+01 9.2000E+01 4.3800E-01 1.3000E-02 21591 2 17 3.9000E+01 9.3000E+01 1.5800E-01 2.0000E-03 21591 2 18 4.0000E+01 9.5000E+01 1.5000E-02 2.0000E-03 21591 2 19 5.6000E+01 1.3900E+02 7.0900E-01 7.0000E-03 21591 2 20 5.6000E+01 1.4000E+02 6.1600E-01 5.0000E-03 21591 2 21 5.7000E+01 1.4200E+02 1.1200E-01 1.1000E-02 21591 2 22 5.8000E+01 1.4100E+02 3.0500E-01 1.4000E-02 21591 2 23 ENDDATA 11 21591 2 24 ENDSUBENT 4 21591 299999 ENDENTRY 2 2159199999999 ENTRY 21708 860206 21708 0 1 SUBENT 21708001 860206 21708 1 1 BIB 13 38 21708 1 2 INSTITUTE (2FR BRC) SERVICE RADIOCHIMIE ET PHENEMOLOGIE. 21708 1 3 REFERENCE (R,CEA-R-5147,8112) MAIN REFERENCE. (IN FRENCH). 21708 1 4 (W,GOUTIERE,810106) PRIVATE COMMUNICATION OF 21708 1 5 G.GOUTIERE WITH THE DETAILED DISCRIPTION OF THE 21708 1 6 EXPERIMENT AND THE DATA. 21708 1 7 (P,NEANDC(E)-172,(4),18,76) ABSTRACT. 21708 1 8 (P,NEANDC(E)-192,(4),28,78) ABSTRACT. 21708 1 9 AUTHOR (J.LAUREC,A.ADAM,T.DEBRUYNE) 21708 1 10 TITLE -DETERMINATION OF THE FIISION YIELDS OF U-233, 21708 1 11 U-235,U-238,PU-239 INDUCED BY A SPECTRA OF FISSION 21708 1 12 NEUTRONS AND NEUTRONS OF 14.7 MEV. 21708 1 13 (DETERMINATION DES RENDEMENTS DE FISSIONS INDUITES 21708 1 14 PAR UN SPECTRE DE NEUTRONS DE FISSION ET DES 21708 1 15 NEUTRONS DE 14.7 MEV DANS U-233,U-235,U-238,PU-239) 21708 1 16 FACILITY .LANCELOT 14 MEV NEUTRON GENERATOR OF C.E.VALDUC. 21708 1 17 INC-SOURCE (D-T ) DEUTERON-TRITIUM REACTION. 21708 1 18 METHOD (CHSEP) RADIOCHEMICAL METHOD. DIRECT MEASUREMENT OF 21708 1 19 THE NUMBER OF FISSIONS AND OF THE FISSION PRODUCT 21708 1 20 ACTIVITIES. 21708 1 21 DETECTOR (FISCH) PLANE FISSION CHAMBER FOR MEASUREMENT OF THE 21708 1 22 NUMBER OF FISSIONS. 21708 1 23 (GELI ) CALIBRATED GE-LI SPECTROMETERS. 21708 1 24 CORRECTION .FOR THE DIFFERENCE OF THE NEUTRON FLUX BETWEEN THE 21708 1 25 FISSION CHAMBER AND THE TARGET DEPOSITS. 21708 1 26 ERR-ANALYS (ERR-T) TOTAL ERROR GIVEN BUT THE ERROR DUE TO THE 21708 1 27 UNCERTAINTIES IN THE BRANCHING RATIOS OF THE 21708 1 28 FISSION PRODUCTS IS NOT INCLUDED. 21708 1 29 .DETAILED CONTRIBUTIONS ARE GIVEN IN TABLE PAGE 35. 21708 1 30 COMMENT .TARGET AND CHAMBER DEPOSIT MASSES ARE DETERMINED BY 21708 1 31 ALPHA AND MASS SPECTROMETRIES. 21708 1 32 STATUS .DATA TAKEN FROM MAIN REFERENCE. 21708 1 33 HISTORY (810114C) G.C. 21708 1 34 (810120E) 21708 1 35 (840806A) MAIN REFERENCE RECEIVED. 21708 1 36 DATA UPDATED AND U-233 DATA ADDED. 21708 1 37 (850419E) 21708 1 38 (850821U)HH 21708 1 39 (860106E) 21708 1 40 ENDBIB 38 21708 1 41 COMMON 1 3 21708 1 42 EN 21708 1 43 MEV 21708 1 44 1.4700E+01 21708 1 45 ENDCOMMON 1 3 21708 1 46 ENDSUBENT 1 21708 199999 SUBENT 21708002 850826 21708 2 1 BIB 3 7 21708 2 2 REACTION (92-U-235(N,F)ELEM/MASS,CUM,FY) RADIOCHEMICALLY 21708 2 3 DETERMINED FISSION YIELDS. 21708 2 4 SAMPLE .U(3)-O(8) TARGETS ON ALUMINIUM FOILS. 21708 2 5 DIAMETER 14 MM, ENRICHMENT 99.9 PERCENT U-235.DETAILS 21708 2 6 OF ISOTOPIC COMPOSITION GIVEN IN TABLE PAGE 18. 21708 2 7 HISTORY (810114C) G.C. 21708 2 8 (810120E) 21708 2 9 ENDBIB 7 21708 2 10 NOCOMMON 0 0 21708 2 11 DATA 4 15 21708 2 12 ELEMENT MASS DATA ERR-T 21708 2 13 NO-DIM NO-DIM PC/FIS PER-CENT 21708 2 14 4.0000E+01 9.5000E+01 5.3300E+00 3.8000E+00 21708 2 15 4.0000E+01 9.7000E+01 5.0300E+00 5.0000E+00 21708 2 16 4.2000E+01 9.9000E+01 5.0500E+00 3.8000E+00 21708 2 17 4.4000E+01 1.0300E+02 3.0800E+00 4.1000E+00 21708 2 18 5.1000E+01 1.2700E+02 1.7600E+00 7.5000E+00 21708 2 19 5.2000E+01 1.3200E+02 4.1400E+00 3.9000E+00 21708 2 20 5.3000E+01 1.3100E+02 4.3200E+00 4.0000E+00 21708 2 21 5.3000E+01 1.3300E+02 5.4300E+00 4.9000E+00 21708 2 22 5.4000E+01 1.3500E+02 4.9700E+00 6.4000E+00 21708 2 23 5.5000E+01 1.3600E+02 2.1600E-01 9.0000E+00 21708 2 24 5.6000E+01 1.4000E+02 4.6100E+00 4.2000E+00 21708 2 25 5.8000E+01 1.4100E+02 4.5000E+00 4.0000E+00 21708 2 26 5.8000E+01 1.4300E+02 3.7500E+00 4.1000E+00 21708 2 27 5.8000E+01 1.4400E+02 3.1500E+00 1.0000E+00 21708 2 28 6.0000E+01 1.4700E+02 1.6200E+00 4.8000E+00 21708 2 29 ENDDATA 17 21708 2 30 ENDSUBENT 4 21708 299999 SUBENT 21708003 850826 21708 3 1 BIB 3 8 21708 3 2 REACTION (92-U-238(N,F)ELEM/MASS,CUM,FY) RADIOCHEMICALLY 21708 3 3 DETERMINED FISSION YIELDS. 21708 3 4 SAMPLE .U(3)-O(8) TARGETS ON ALUMINIUM FOILS. 21708 3 5 TARGET DIAMETER 14 MM, ENRICHMENT 99.9 PERCENT U-238. 21708 3 6 .DETAILS OF ISOTOPIC COMPOSITION GIVEN IN 21708 3 7 TABLE PAGE 18. 21708 3 8 HISTORY (810114C) G.C. 21708 3 9 (810120E) 21708 3 10 ENDBIB 8 21708 3 11 NOCOMMON 0 0 21708 3 12 DATA 4 15 21708 3 13 ELEMENT MASS DATA ERR-T 21708 3 14 NO-DIM NO-DIM PC/FIS PER-CENT 21708 3 15 4.0000E+01 9.5000E+01 4.9700E+00 4.2000E+00 21708 3 16 4.0000E+01 9.7000E+01 5.2300E+00 4.8000E+00 21708 3 17 4.2000E+01 9.9000E+01 5.7500E+00 3.9000E+00 21708 3 18 4.4000E+01 1.0300E+02 4.7400E+00 4.0000E+00 21708 3 19 4.5000E+01 1.0500E+02 3.4000E+00 6.0000E+00 21708 3 20 5.1000E+01 1.2700E+02 1.3800E+00 5.2000E+00 21708 3 21 5.2000E+01 1.3200E+02 4.7200E+00 3.9000E+00 21708 3 22 5.3000E+01 1.3100E+02 4.0500E+00 4.3000E+00 21708 3 23 5.3000E+01 1.3300E+02 5.5000E+00 6.0000E+00 21708 3 24 5.4000E+01 1.3500E+02 5.7000E+00 5.0000E+00 21708 3 25 5.6000E+01 1.4000E+02 4.6500E+00 4.2000E+00 21708 3 26 5.8000E+01 1.4100E+02 4.4400E+00 4.0000E+00 21708 3 27 5.8000E+01 1.4300E+02 3.9400E+00 4.5000E+00 21708 3 28 5.8000E+01 1.4400E+02 3.7200E+00 7.0000E+00 21708 3 29 6.0000E+01 1.4700E+02 2.0800E+00 4.7000E+00 21708 3 30 ENDDATA 17 21708 3 31 ENDSUBENT 4 21708 399999 SUBENT 21708004 850826 21708 4 1 BIB 3 8 21708 4 2 REACTION (94-PU-239(N,F)ELEM/MASS,CUM,FY) RADIOCHEMICALLY 21708 4 3 DETERMINED FISSION YIELDS. 21708 4 4 SAMPLE .PU-O(2) TARGETS ON ALUMINIUM FOILS. 21708 4 5 TARGET DIAMETER 14 MM, ENRICHMENT IN PU-239 21708 4 6 BETTER THAN 98. PERCENT. DETAILS OF ISOTOPIC 21708 4 7 COMPOSITION GIVEN IN TABLE PAGE 18. 21708 4 8 HISTORY (810114C) G.C. 21708 4 9 (810120E) 21708 4 10 ENDBIB 8 21708 4 11 NOCOMMON 0 0 21708 4 12 DATA 4 15 21708 4 13 ELEMENT MASS DATA ERR-T 21708 4 14 NO-DIM NO-DIM PC/FIS PER-CENT 21708 4 15 4.0000E+01 9.5000E+01 3.9600E+00 3.9000E+00 21708 4 16 4.0000E+01 9.7000E+01 4.4000E+00 4.5000E+00 21708 4 17 4.2000E+01 9.9000E+01 5.0400E+00 3.6000E+00 21708 4 18 4.4000E+01 1.0300E+02 5.3000E+00 3.7000E+00 21708 4 19 4.5000E+01 1.0500E+02 4.3000E+00 4.6000E+00 21708 4 20 5.1000E+01 1.2700E+02 2.1700E+00 4.4000E+00 21708 4 21 5.2000E+01 1.3200E+02 3.1500E+00 3.7000E+00 21708 4 22 5.3000E+01 1.3100E+02 4.5500E+00 4.8000E+00 21708 4 23 5.3000E+01 1.3300E+02 4.2500E+00 9.0000E+00 21708 4 24 5.4000E+01 1.3600E+02 7.9700E-01 4.4000E+00 21708 4 25 5.6000E+01 1.4000E+02 3.6000E+00 3.8000E+00 21708 4 26 5.8000E+01 1.4100E+02 3.6800E+00 4.1000E+00 21708 4 27 5.8000E+01 1.4300E+02 2.9300E+00 4.0000E+00 21708 4 28 5.8000E+01 1.4400E+02 2.5900E+00 7.3000E+00 21708 4 29 6.0000E+01 1.4700E+02 1.6400E+00 4.2000E+00 21708 4 30 ENDDATA 17 21708 4 31 ENDSUBENT 4 21708 499999 SUBENT 21708005 850826 21708 5 1 BIB 3 8 21708 5 2 REACTION (92-U-233(N,F)ELEM/MASS,CUM,FY) RADIOCHEMICALLY 21708 5 3 DETERMINED FISSION YIELDS. 21708 5 4 SAMPLE .U(3)-O(8) TARGETS ON ALUMINIUM FOILS. 21708 5 5 TARGET DIAMETER 14 MM, ENRICHMENT 99.9 PERCENT U-233. 21708 5 6 .DETAILS OF ISOTOPIC COMPOSITION GIVEN 21708 5 7 .IN TABLE PAGE 18. 21708 5 8 HISTORY (840806C) BN. 21708 5 9 (850419E) 21708 5 10 ENDBIB 8 21708 5 11 NOCOMMON 0 0 21708 5 12 DATA 4 13 21708 5 13 ELEMENT MASS DATA ERR-T 21708 5 14 NO-DIM NO-DIM PC/FIS PER-CENT 21708 5 15 4.0000E+01 9.5000E+01 5.1300E+00 5.5000E+00 21708 5 16 4.0000E+01 9.7000E+01 4.8500E+00 5.7000E+00 21708 5 17 4.2000E+01 9.9000E+01 4.4000E+00 5.0000E+00 21708 5 18 4.4000E+01 1.0300E+02 2.8100E+00 5.3000E+00 21708 5 19 5.2000E+01 1.3200E+02 3.1400E+00 5.3000E+00 21708 5 20 5.3000E+01 1.3100E+02 4.6300E+00 5.3000E+00 21708 5 21 5.4000E+01 1.3500E+02 3.4600E+00 7.0000E+00 21708 5 22 5.5000E+01 1.3600E+02 8.3700E-01 6.0000E+00 21708 5 23 5.6000E+01 1.4000E+02 4.3900E+00 5.7000E+00 21708 5 24 5.8000E+01 1.4100E+02 4.2400E+00 6.1000E+00 21708 5 25 5.8000E+01 1.4300E+02 3.1700E+00 5.5000E+00 21708 5 26 5.8000E+01 1.4400E+02 2.4300E+00 8.0000E+00 21708 5 27 6.0000E+01 1.4700E+02 1.3200E+00 6.5000E+00 21708 5 28 ENDDATA 15 21708 5 29 ENDSUBENT 4 21708 599999 ENDENTRY 5 2170899999999 ENTRY 21734 810723 21734 0 1 SUBENT 21734001 810723 21734 1 1 BIB 13 41 21734 1 2 INSTITUTE (2FR GRE) LABORATOIRE DE CHIMIE NUCLEAIRE. 21734 1 3 REFERENCE (J,NP/A,189,556,7207) TABLES. 21734 1 4 (C,71CANT,13,7109) TABLE OF CUMULATIVE YIELDS. 21734 1 5 (T,BOCQUET,71) THESIS, A.O.6032, CNRS. 21734 1 6 AUTHOR (J.P.BOCQUET,R.BRISSOT,J.CRANCON,A.MOUSSA) 21734 1 7 TITLE -ON-LINE MEASUREMENTS OF RARE-GAS FISSION YIELDS 21734 1 8 IN 14 MEV NEUTRON FISSION -. 21734 1 9 FACILITY .SAMES 14 MEV NEUTRON GENERATOR. 21734 1 10 INC-SOURCE (D-T ) ELECTROSTATICALLY ACCELERATED DEUTERON 21734 1 11 BEAM ON SOLID TITANIUM TRITIDE TARGET. 21734 1 12 SAMPLE .SAMPLES OF TH-232 AND U-233 WERE NEARLY 100 PERCENT 21734 1 13 PURE, U-235 WAS ENRICHED TO 93 PERCENT AND CONTAINED 21734 1 14 SEVEN PERCENT OF U-238. THE U-238 WAS NATURAL 21734 1 15 URANIUM, WITH NO CORRECTION MADE FOR THE U-235 21734 1 16 CONTENT. 21734 1 17 METHOD (ASEP ) ON LINE ISOTOPE SEPERATOR, ISOL. 21734 1 18 (ACTIV) QUANTITATIVE MEASUREMENTS OF RARE-GAS 21734 1 19 ACTIVITIES WERE PERFORMED USING A 4 PI BETA-COUNTING 21734 1 20 DEVICE DETECTING FISSION PRODUCT ACTIVITIES ON A 21734 1 21 MOVING TAPE LOCATED AT THE END OF THE ISOTOPE 21734 1 22 SEPERATOR. 21734 1 23 .TWO SOURCES WERE COLLECTED FROM EACH IRRADIATION, 21734 1 24 THE FIRST WAS COLLECTED DURING IRRADIATION AND 21734 1 25 COUNTED, THE SECOND WAS COLLECTED AFTER IRRADIATION 21734 1 26 AND WAS COUNTED TO ALLOW SEPERATION OF INDEPENDENT 21734 1 27 AND CUMULATIVE YIELDS. 21734 1 28 .INDEPENDENT YIELDS ARE DERIVED FROM THE MEASURED 21734 1 29 RATIOS OF INDEPENDENT YIELDS OF XE AND KR TO THE 21734 1 30 CORRESPONDING CUMULATIVE YIELDS OF I AND BR. 21734 1 31 DETECTOR (PROPC) PROPORTIONAL COUNTER FOR BETA DETECTION. 21734 1 32 ALL DECAY PARAMETERS ARE TAKEN FROM CARLSON AND 21734 1 33 TALBOT, NP/A,125,267,1969. 21734 1 34 CORRECTION .CORRECTIONS WERE MADE FOR THE BEHAVIOUR OF THE RARE 21734 1 35 GASES THROUGH THE ON-LINE SYSTEM, FOR DAUGHTER 21734 1 36 ACTIVITY GROWING AT THE COLLECTOR END, AND FOR 21734 1 37 COUNTING LOSSES DUE TO ABSORPTION OF BETAS. 21734 1 38 ERR-ANALYS .TOTAL ABSOLUTE UNCERTAINTIES ARE GIVEN AT ONE 21734 1 39 STANDARD DEVIATION. 21734 1 40 STATUS .TABLES IN NP/A,189,556. 21734 1 41 HISTORY (810127C) 21734 1 42 (810213E) 21734 1 43 ENDBIB 41 21734 1 44 COMMON 1 3 21734 1 45 EN 21734 1 46 MEV 21734 1 47 1.4500E+01 21734 1 48 ENDCOMMON 1 3 21734 1 49 ENDSUBENT 1 21734 199999 SUBENT 21734002 810213 21734 2 1 BIB 4 7 21734 2 2 REACTION (90-TH-232(N,F)ELEM/MASS,IND,FY) INDEPENDENT 21734 2 3 FISSION YIELDS. 21734 2 4 MONITOR (90-TH-232(N,F)36-KR-91,IND,FY) VALUE TAKEN 21734 2 5 AS 3.13+-0.2 PC/FIS. 21734 2 6 STATUS .TABLE 2. 21734 2 7 HISTORY (810127C) 21734 2 8 (810213E) 21734 2 9 ENDBIB 7 21734 2 10 COMMON 2 3 21734 2 11 MONIT MONIT-ERR 21734 2 12 PC/FIS PC/FIS 21734 2 13 3.1300E+00 2.0000E-01 21734 2 14 ENDCOMMON 2 3 21734 2 15 DATA 4 6 21734 2 16 ELEMENT MASS DATA DATA-ERR 21734 2 17 NO-DIM NO-DIM PC/FIS PC/FIS 21734 2 18 3.6000E+01 8.7000E+01 4.6000E-01 9.0000E-02 21734 2 19 3.6000E+01 8.8000E+01 1.9800E+00 3.0000E-01 21734 2 20 3.6000E+01 8.9000E+01 2.7000E+00 3.0000E-01 21734 2 21 3.6000E+01 9.0000E+01 3.6200E+00 4.0000E-01 21734 2 22 3.6000E+01 9.2000E+01 2.0300E+00 2.0000E-01 21734 2 23 3.6000E+01 9.3000E+01 7.0000E-01 1.0000E-01 21734 2 24 ENDDATA 8 21734 2 25 ENDSUBENT 4 21734 299999 SUBENT 21734003 810213 21734 3 1 BIB 4 7 21734 3 2 REACTION (90-TH-232(N,F)ELEM/MASS,IND,FY) INDEPENDENT 21734 3 3 FISSION YIELDS. 21734 3 4 MONITOR (90-TH-232(N,F)54-XE-137,IND,FY) VALUE TAKEN 21734 3 5 AS 1.86+-0.25 PC/FIS. 21734 3 6 STATUS .TABLE 2. 21734 3 7 HISTORY (810127C) 21734 3 8 (810213E) 21734 3 9 ENDBIB 7 21734 3 10 COMMON 3 3 21734 3 11 ELEMENT MONIT MONIT-ERR 21734 3 12 NO-DIM PC/FIS PC/FIS 21734 3 13 5.4000E+01 1.8600E+00 2.5000E-01 21734 3 14 ENDCOMMON 3 3 21734 3 15 DATA 3 5 21734 3 16 MASS DATA DATA-ERR 21734 3 17 NO-DIM PC/FIS PC/FIS 21734 3 18 1.3800E+02 2.7500E+00 6.0000E-01 21734 3 19 1.3900E+02 3.3800E+00 4.5000E-01 21734 3 20 1.4000E+02 3.1200E+00 4.0000E-01 21734 3 21 1.4100E+02 1.4400E+00 2.0000E-01 21734 3 22 1.4200E+02 7.3000E-01 1.3000E-01 21734 3 23 ENDDATA 7 21734 3 24 ENDSUBENT 3 21734 399999 SUBENT 21734004 810213 21734 4 1 BIB 4 7 21734 4 2 REACTION (92-U-233(N,F)ELEM/MASS,IND,FY) INDEPENDENT 21734 4 3 FISSION YIELDS. 21734 4 4 MONITOR (92-U-233(N,F)36-KR-90,IND,FY) VALUE TAKEN 21734 4 5 AS 2.3+-0.3 PC/FIS. 21734 4 6 STATUS .TABLE 2. 21734 4 7 HISTORY (810127C) 21734 4 8 (810213E) 21734 4 9 ENDBIB 7 21734 4 10 COMMON 3 3 21734 4 11 ELEMENT MONIT MONIT-ERR 21734 4 12 NO-DIM PC/FIS PC/FIS 21734 4 13 3.6000E+01 2.3000E+00 3.0000E-01 21734 4 14 ENDCOMMON 3 3 21734 4 15 DATA 3 6 21734 4 16 MASS DATA DATA-ERR 21734 4 17 NO-DIM PC/FIS PC/FIS 21734 4 18 8.7000E+01 1.9100E+00 3.0000E-01 21734 4 19 8.8000E+01 2.5700E+00 4.0000E-01 21734 4 20 8.9000E+01 3.1700E+00 5.0000E-01 21734 4 21 9.1000E+01 1.2000E+00 1.5000E-01 21734 4 22 9.2000E+01 4.7000E-01 1.0000E-01 21734 4 23 9.3000E+01 1.0000E-01 3.0000E-02 21734 4 24 ENDDATA 8 21734 4 25 ENDSUBENT 3 21734 499999 SUBENT 21734005 810213 21734 5 1 BIB 4 7 21734 5 2 REACTION (92-U-233(N,F)ELEM/MASS,IND,FY) INDEPENDENT 21734 5 3 FISSION YIELDS. 21734 5 4 MONITOR (92-U-233(N,F)54-XE-137,IND,FY) VALUE TAKEN 21734 5 5 AS 3.15+-0.3 PC/FIS. 21734 5 6 STATUS .TABLE 2. 21734 5 7 HISTORY (810127C) 21734 5 8 (810213E) 21734 5 9 ENDBIB 7 21734 5 10 COMMON 3 3 21734 5 11 ELEMENT MONIT MONIT-ERR 21734 5 12 NO-DIM PC/FIS PC/FIS 21734 5 13 5.4000E+01 3.1500E+00 3.0000E-01 21734 5 14 ENDCOMMON 3 3 21734 5 15 DATA 3 4 21734 5 16 MASS DATA DATA-ERR 21734 5 17 NO-DIM PC/FIS PC/FIS 21734 5 18 1.3800E+02 1.9200E+00 2.0000E-01 21734 5 19 1.3900E+02 9.8000E-01 1.0000E-01 21734 5 20 1.4000E+02 3.9000E-01 4.0000E-02 21734 5 21 1.4100E+02 9.4000E-02 2.0000E-02 21734 5 22 ENDDATA 6 21734 5 23 ENDSUBENT 3 21734 599999 SUBENT 21734006 810213 21734 6 1 BIB 4 7 21734 6 2 REACTION (92-U-235(N,F)ELEM/MASS,IND,FY) INDEPENDENT 21734 6 3 FISSION YIELDS. 21734 6 4 MONITOR (92-U-235(N,F)36-KR-90,IND,FY) VALUE TAKEN 21734 6 5 AS 2.45+-0.42 PC/FIS. 21734 6 6 STATUS .TABLE 2. 21734 6 7 HISTORY (810127C) 21734 6 8 (810213E) 21734 6 9 ENDBIB 7 21734 6 10 COMMON 3 3 21734 6 11 ELEMENT MONIT MONIT-ERR 21734 6 12 NO-DIM PC/FIS PC/FIS 21734 6 13 3.6000E+01 2.4500E+00 4.2000E-01 21734 6 14 ENDCOMMON 3 3 21734 6 15 DATA 3 6 21734 6 16 MASS DATA DATA-ERR 21734 6 17 NO-DIM PC/FIS PC/FIS 21734 6 18 8.7000E+01 8.4000E-01 1.5000E-01 21734 6 19 8.8000E+01 1.3400E+00 2.6000E-01 21734 6 20 8.9000E+01 2.5500E+00 4.4000E-01 21734 6 21 9.1000E+01 1.7600E+00 3.3000E-01 21734 6 22 9.2000E+01 8.1000E-01 1.4000E-01 21734 6 23 9.3000E+01 2.1000E-01 4.0000E-02 21734 6 24 ENDDATA 8 21734 6 25 ENDSUBENT 3 21734 699999 SUBENT 21734007 810213 21734 7 1 BIB 4 7 21734 7 2 REACTION (92-U-235(N,F)ELEM/MASS,IND,FY) INDEPENDENT 21734 7 3 FISSION YIELDS. 21734 7 4 MONITOR (92-U-235(N,F)54-XE-137,IND,FY) VALUE TAKEN 21734 7 5 AS 3.13+-0.50 PC/FIS. 21734 7 6 STATUS .TABLE 2. 21734 7 7 HISTORY (810127C) 21734 7 8 (810213E) 21734 7 9 ENDBIB 7 21734 7 10 COMMON 3 3 21734 7 11 ELEMENT MONIT MONIT-ERR 21734 7 12 NO-DIM PC/FIS PC/FIS 21734 7 13 5.4000E+01 3.1300E+00 5.0000E-01 21734 7 14 ENDCOMMON 3 3 21734 7 15 DATA 3 5 21734 7 16 MASS DATA DATA-ERR 21734 7 17 NO-DIM PC/FIS PC/FIS 21734 7 18 1.3800E+02 2.6000E+00 4.5000E-01 21734 7 19 1.3900E+02 1.8000E+00 3.0000E-01 21734 7 20 1.4000E+02 9.6000E-01 1.5000E-01 21734 7 21 1.4100E+02 2.5000E-01 4.0000E-02 21734 7 22 1.4200E+02 9.1000E-02 1.5000E-02 21734 7 23 ENDDATA 7 21734 7 24 ENDSUBENT 3 21734 799999 SUBENT 21734008 810213 21734 8 1 BIB 4 7 21734 8 2 REACTION (92-U-238(N,F)ELEM/MASS,IND,FY) INDEPENDENT 21734 8 3 FISSION YIELDS. 21734 8 4 MONITOR (92-U-238(N,F)36-KR-90,IND,FY) VALUE TAKEN 21734 8 5 AS 1.88+-0.22 PC/FIS. 21734 8 6 STATUS .TABLE 2. 21734 8 7 HISTORY (810127C) 21734 8 8 (810213E) 21734 8 9 ENDBIB 7 21734 8 10 COMMON 3 3 21734 8 11 ELEMENT MONIT MONIT-ERR 21734 8 12 NO-DIM PC/FIS PC/FIS 21734 8 13 3.6000E+01 1.8800E+00 2.2000E-01 21734 8 14 ENDCOMMON 3 3 21734 8 15 DATA 3 6 21734 8 16 MASS DATA DATA-ERR 21734 8 17 NO-DIM PC/FIS PC/FIS 21734 8 18 8.7000E+01 7.9000E-02 2.0000E-02 21734 8 19 8.8000E+01 6.0000E-01 7.0000E-02 21734 8 20 8.9000E+01 1.4000E+00 1.9000E-01 21734 8 21 9.1000E+01 2.0400E+00 2.2000E-01 21734 8 22 9.2000E+01 1.6600E+00 2.0000E-01 21734 8 23 9.3000E+01 7.3000E-01 9.0000E-02 21734 8 24 ENDDATA 8 21734 8 25 ENDSUBENT 3 21734 899999 SUBENT 21734009 810213 21734 9 1 BIB 4 7 21734 9 2 REACTION (92-U-238(N,F)ELEM/MASS,IND,FY) INDEPENDENT 21734 9 3 FISSION YIELDS. 21734 9 4 MONITOR (92-U-238(N,F)54-XE-137,IND,FY) VALUE TAKEN 21734 9 5 AS 1.66+-0.12 PC/FIS. 21734 9 6 STATUS .TABLE 2. 21734 9 7 HISTORY (810127C) 21734 9 8 (810213E) 21734 9 9 ENDBIB 7 21734 9 10 COMMON 3 3 21734 9 11 ELEMENT MONIT MONIT-ERR 21734 9 12 NO-DIM PC/FIS PC/FIS 21734 9 13 5.4000E+01 1.6600E+00 1.2000E-01 21734 9 14 ENDCOMMON 3 3 21734 9 15 DATA 3 5 21734 9 16 MASS DATA DATA-ERR 21734 9 17 NO-DIM PC/FIS PC/FIS 21734 9 18 1.3800E+02 2.3900E+00 1.7000E-01 21734 9 19 1.3900E+02 2.6600E+00 1.8000E-01 21734 9 20 1.4000E+02 2.5200E+00 1.7000E-01 21734 9 21 1.4100E+02 1.2800E+00 1.1000E-01 21734 9 22 1.4200E+02 6.8000E-01 9.0000E-02 21734 9 23 ENDDATA 7 21734 9 24 ENDSUBENT 3 21734 999999 SUBENT 21734010 810213 21734 10 1 BIB 3 6 21734 10 2 REACTION (92-U-233(N,F)ELEM/MASS,CUM,FY,,REL) RELATIVE 21734 10 3 CUMULATIVE FISSION YIELDS RELATIVE TO UNITY 21734 10 4 FOR KR-90. 21734 10 5 STATUS .TABLE 1. 21734 10 6 HISTORY (810127C) 21734 10 7 (810213E) 21734 10 8 ENDBIB 6 21734 10 9 COMMON 1 3 21734 10 10 ELEMENT 21734 10 11 NO-DIM 21734 10 12 3.6000E+01 21734 10 13 ENDCOMMON 1 3 21734 10 14 DATA 3 7 21734 10 15 MASS DATA DATA-ERR 21734 10 16 NO-DIM ARB-UNITS ARB-UNITS 21734 10 17 8.7000E+01 1.4400E+00 3.0000E-02 21734 10 18 8.8000E+01 1.4600E+00 5.0000E-02 21734 10 19 8.9000E+01 1.4500E+00 4.0000E-02 21734 10 20 9.0000E+01 1.0000E+00 2.0000E-02 21734 10 21 9.1000E+01 4.9000E-01 1.0000E-02 21734 10 22 9.2000E+01 1.9300E-01 1.0000E-02 21734 10 23 9.3000E+01 4.1000E-02 1.0000E-02 21734 10 24 ENDDATA 9 21734 10 25 ENDSUBENT 3 21734 1099999 SUBENT 21734011 810213 21734 11 1 BIB 3 5 21734 11 2 REACTION (92-U-233(N,F)ELEM/MASS,CUM,FY,,REL) 21734 11 3 CUMULATIVE FISSION YIELDS RELATIVE TO UNITY FOR XE-13 21734 11 4 STATUS .TABLE 1. 21734 11 5 HISTORY (810127C) 21734 11 6 (810213E) 21734 11 7 ENDBIB 5 21734 11 8 COMMON 1 3 21734 11 9 ELEMENT 21734 11 10 NO-DIM 21734 11 11 5.4000E+01 21734 11 12 ENDCOMMON 1 3 21734 11 13 DATA 3 5 21734 11 14 MASS DATA DATA-ERR 21734 11 15 NO-DIM ARB-UNITS ARB-UNITS 21734 11 16 1.3700E+02 1.0000E+00 2.0000E-02 21734 11 17 1.3800E+02 6.0000E-01 1.0000E-02 21734 11 18 1.3900E+02 2.8300E-01 1.0000E-02 21734 11 19 1.4000E+02 1.0700E-01 3.0000E-03 21734 11 20 1.4100E+02 2.5200E-02 1.5000E-03 21734 11 21 ENDDATA 7 21734 11 22 ENDSUBENT 3 21734 1199999 SUBENT 21734012 810213 21734 12 1 BIB 3 5 21734 12 2 REACTION (92-U-235(N,F)ELEM/MASS,CUM,FY,,REL) 21734 12 3 CUMULATIVE FISSION YIELDS RELATIVE TO UNITY FOR KR-90 21734 12 4 STATUS .TABLE 1. 21734 12 5 HISTORY (810127C) 21734 12 6 (810213E) 21734 12 7 ENDBIB 5 21734 12 8 COMMON 1 3 21734 12 9 ELEMENT 21734 12 10 NO-DIM 21734 12 11 3.6000E+01 21734 12 12 ENDCOMMON 1 3 21734 12 13 DATA 3 7 21734 12 14 MASS DATA DATA-ERR 21734 12 15 NO-DIM ARB-UNITS ARB-UNITS 21734 12 16 8.7000E+01 9.2600E-01 3.0000E-02 21734 12 17 8.8000E+01 9.0300E-01 4.0000E-02 21734 12 18 8.9000E+01 1.1720E+00 2.0000E-02 21734 12 19 9.0000E+01 1.0000E+00 2.0000E-02 21734 12 20 9.1000E+01 6.1000E-01 2.0000E-02 21734 12 21 9.2000E+01 2.7900E-01 1.0000E-02 21734 12 22 9.3000E+01 7.2000E-02 4.0000E-03 21734 12 23 ENDDATA 9 21734 12 24 ENDSUBENT 3 21734 1299999 SUBENT 21734013 810213 21734 13 1 BIB 3 6 21734 13 2 REACTION (92-U-235(N,F)ELEM/MASS,CUM,FY,,REL) 21734 13 3 CUMULATIVE FISSION YIELDS RELATIVE TO UNITY 21734 13 4 FOR XE-137. 21734 13 5 STATUS .TABLE 1. 21734 13 6 HISTORY (810127C) 21734 13 7 (810213E) 21734 13 8 ENDBIB 6 21734 13 9 COMMON 1 3 21734 13 10 ELEMENT 21734 13 11 NO-DIM 21734 13 12 5.4000E+01 21734 13 13 ENDCOMMON 1 3 21734 13 14 DATA 3 6 21734 13 15 MASS DATA DATA-ERR 21734 13 16 NO-DIM ARB-UNITS ARB-UNITS 21734 13 17 1.3700E+02 1.0000E+00 2.0000E-02 21734 13 18 1.3800E+02 7.5500E-01 2.0000E-02 21734 13 19 1.3900E+02 4.6500E-01 2.0000E-02 21734 13 20 1.4000E+02 2.2200E-01 6.0000E-03 21734 13 21 1.4100E+02 5.7000E-02 4.0000E-03 21734 13 22 1.4200E+02 2.0500E-02 2.0000E-03 21734 13 23 ENDDATA 8 21734 13 24 ENDSUBENT 3 21734 1399999 SUBENT 21734014 810213 21734 14 1 BIB 3 5 21734 14 2 REACTION (92-U-238(N,F)ELEM/MASS,CUM,FY,,REL) 21734 14 3 CUMULATIVE FISSION YIELDS RELATIVE TO UNITY FOR KR-90 21734 14 4 STATUS .TABLE 1. 21734 14 5 HISTORY (810127C) 21734 14 6 (810213E) 21734 14 7 ENDBIB 5 21734 14 8 COMMON 1 3 21734 14 9 ELEMENT 21734 14 10 NO-DIM 21734 14 11 3.6000E+01 21734 14 12 ENDCOMMON 1 3 21734 14 13 DATA 3 7 21734 14 14 MASS DATA DATA-ERR 21734 14 15 NO-DIM ARB-UNITS ARB-UNITS 21734 14 16 8.7000E+01 6.6000E-01 2.0000E-02 21734 14 17 8.8000E+01 7.1000E-01 3.0000E-02 21734 14 18 8.9000E+01 9.8000E-01 1.0000E-02 21734 14 19 9.0000E+01 1.0000E+00 3.0000E-02 21734 14 20 9.1000E+01 9.4000E-01 1.0000E-02 21734 14 21 9.2000E+01 7.0000E-01 3.0000E-02 21734 14 22 9.3000E+01 3.0000E-01 2.0000E-02 21734 14 23 ENDDATA 9 21734 14 24 ENDSUBENT 3 21734 1499999 SUBENT 21734015 810213 21734 15 1 BIB 3 6 21734 15 2 REACTION (92-U-238(N,F)ELEM/MASS,CUM,FY,,REL) 21734 15 3 CUMULATIVE FISSION YIELDS RELATIVE TO UNITY 21734 15 4 FOR XE-137. 21734 15 5 STATUS .TABLE 1. 21734 15 6 HISTORY (810127C) 21734 15 7 (810213E) 21734 15 8 ENDBIB 6 21734 15 9 COMMON 1 3 21734 15 10 ELEMENT 21734 15 11 NO-DIM 21734 15 12 5.4000E+01 21734 15 13 ENDCOMMON 1 3 21734 15 14 DATA 3 6 21734 15 15 MASS DATA DATA-ERR 21734 15 16 NO-DIM ARB-UNITS ARB-UNITS 21734 15 17 1.3700E+02 1.0000E+00 2.0000E-02 21734 15 18 1.3800E+02 9.1000E-01 2.0000E-02 21734 15 19 1.3900E+02 7.9000E-01 2.0000E-02 21734 15 20 1.4000E+02 5.9000E-01 2.0000E-02 21734 15 21 1.4100E+02 2.7000E-01 1.0000E-02 21734 15 22 1.4200E+02 1.3800E-01 1.0000E-02 21734 15 23 ENDDATA 8 21734 15 24 ENDSUBENT 3 21734 1599999 SUBENT 21734016 810213 21734 16 1 BIB 3 5 21734 16 2 REACTION (90-TH-232(N,F)ELEM/MASS,CUM,FY,,REL) 21734 16 3 CUMULATIVE FISSION YIELDS RELATIVE TO UNITY FOR KR-91 21734 16 4 STATUS .TABLE 1. 21734 16 5 HISTORY (810127C) 21734 16 6 (810213E) 21734 16 7 ENDBIB 5 21734 16 8 COMMON 1 3 21734 16 9 ELEMENT 21734 16 10 NO-DIM 21734 16 11 3.6000E+01 21734 16 12 ENDCOMMON 1 3 21734 16 13 DATA 3 7 21734 16 14 MASS DATA DATA-ERR 21734 16 15 NO-DIM ARB-UNITS ARB-UNITS 21734 16 16 8.7000E+01 1.3200E+00 4.0000E-02 21734 16 17 8.8000E+01 1.4700E+00 7.0000E-02 21734 16 18 8.9000E+01 1.5000E+00 5.0000E-02 21734 16 19 9.0000E+01 1.3500E+00 4.0000E-02 21734 16 20 9.1000E+01 1.0000E+00 2.0000E-02 21734 16 21 9.2000E+01 6.0700E-01 2.0000E-02 21734 16 22 9.3000E+01 2.0400E-01 1.0000E-02 21734 16 23 ENDDATA 9 21734 16 24 ENDSUBENT 3 21734 1699999 SUBENT 21734017 810213 21734 17 1 BIB 3 6 21734 17 2 REACTION (90-TH-232(N,F)ELEM/MASS,CUM,FY,,REL) 21734 17 3 CUMULATIVE FISSION YIELDS RELATIVE TO UNITY 21734 17 4 FOR XE-137. 21734 17 5 STATUS .TABLE 1. 21734 17 6 HISTORY (810127C) 21734 17 7 (810213E) 21734 17 8 ENDBIB 6 21734 17 9 COMMON 1 3 21734 17 10 ELEMENT 21734 17 11 NO-DIM 21734 17 12 5.4000E+01 21734 17 13 ENDCOMMON 1 3 21734 17 14 DATA 3 6 21734 17 15 MASS DATA DATA-ERR 21734 17 16 NO-DIM ARB-UNITS ARB-UNITS 21734 17 17 1.3700E+02 1.0000E+00 1.0000E-02 21734 17 18 1.3800E+02 9.5300E-01 1.0000E-02 21734 17 19 1.3900E+02 9.0500E-01 2.0000E-02 21734 17 20 1.4000E+02 7.2800E-01 1.0000E-02 21734 17 21 1.4100E+02 3.1800E-01 1.0000E-02 21734 17 22 1.4200E+02 1.5800E-01 1.5000E-02 21734 17 23 ENDDATA 8 21734 17 24 ENDSUBENT 3 21734 1799999 SUBENT 21734018 810213 21734 18 1 BIB 4 11 21734 18 2 REACTION (92-U-235(N,F)MASS,CHN,FY) ABSOLUTE CHAIN YIELDS. 21734 18 3 ANALYSIS .RELATIVE CHAIN YIELDS ARE DERIVED FROM THE RELATIVE 21734 18 4 CUMULATIVE YIELDS OF KR AND XE, TOGETHER WITH 21734 18 5 MEASURED OR EXTRAPOLATED FRACTIONAL CUMULATIVE YIELDS 21734 18 6 .ABSOLUTE YIELDS ARE OBTAINED BY NORMALISING WITH A 21734 18 7 FACTOR FROM THE WEIGHTED AVERAGES OF THE RATIOS 21734 18 8 BETWEEN THESE YIELDS AND ABSOLUTE YIELDS FROM 21734 18 9 MEEK AND RYDER, APED 5398A (1968). 21734 18 10 STATUS .TABLE 4A, COLUMN 3. 21734 18 11 HISTORY (810127C) 21734 18 12 (810213E) 21734 18 13 ENDBIB 11 21734 18 14 NOCOMMON 0 0 21734 18 15 DATA 3 12 21734 18 16 MASS DATA DATA-ERR 21734 18 17 NO-DIM PC/FIS PC/FIS 21734 18 18 8.7000E+01 2.8000E+00 2.0000E-01 21734 18 19 8.8000E+01 2.8000E+00 2.0000E-01 21734 18 20 8.9000E+01 4.0000E+00 3.0000E-01 21734 18 21 9.0000E+01 4.6500E+00 3.0000E-01 21734 18 22 9.1000E+01 5.0000E+00 4.5000E-01 21734 18 23 9.2000E+01 5.3000E+00 5.5000E-01 21734 18 24 9.3000E+01 5.5000E+00 7.0000E-01 21734 18 25 1.3700E+02 4.9000E+00 2.0000E-01 21734 18 26 1.3800E+02 4.5100E+00 3.0000E-01 21734 18 27 1.3900E+02 4.8500E+00 2.0000E-01 21734 18 28 1.4000E+02 4.8500E+00 4.0000E-01 21734 18 29 1.4100E+02 4.5600E+00 5.0000E-01 21734 18 30 ENDDATA 14 21734 18 31 ENDSUBENT 3 21734 1899999 SUBENT 21734019 810213 21734 19 1 BIB 4 11 21734 19 2 REACTION (92-U-238(N,F)MASS,CHN,FY) ABSOLUTE CHAIN YIELDS. 21734 19 3 ANALYSIS .RELATIVE CHAIN YIELDS ARE DERIVED FROM RELATIVE 21734 19 4 CUMULATIVE YIELDS TOGETHER WITH MEASURED OR EXTRAPOL- 21734 19 5 ATED FRACTIONAL CUMULATIVE YIELDS. ABSOLUTE YIELDS 21734 19 6 ARE OBTAINED BY NORMALISING WITH A FACTOR FROM THE 21734 19 7 WEIGHTED AVERAGES OF THE RATIOS BETWEEN THESE RELATIV 21734 19 8 YIELDS AND ABSOLUTE YIELDS FROM MEEK AND RYDER, 21734 19 9 APED 5398A (1968). 21734 19 10 STATUS .TABLE 4A, COLUMN 3. 21734 19 11 HISTORY (810127C) 21734 19 12 (810213E) 21734 19 13 ENDBIB 11 21734 19 14 NOCOMMON 0 0 21734 19 15 DATA 3 12 21734 19 16 MASS DATA DATA-ERR 21734 19 17 NO-DIM PC/FIS PC/FIS 21734 19 18 8.7000E+01 1.6300E+00 1.3000E-01 21734 19 19 8.8000E+01 1.7700E+00 1.5000E-01 21734 19 20 8.9000E+01 2.5200E+00 2.2000E-01 21734 19 21 9.0000E+01 2.8600E+00 2.6000E-01 21734 19 22 9.1000E+01 3.6000E+00 3.0000E-01 21734 19 23 9.2000E+01 3.9400E+00 4.3000E-01 21734 19 24 9.3000E+01 4.5500E+00 6.5000E-01 21734 19 25 1.3700E+02 5.0600E+00 2.5000E-01 21734 19 26 1.3800E+02 4.8600E+00 3.0000E-01 21734 19 27 1.3900E+02 4.9100E+00 3.0000E-01 21734 19 28 1.4000E+02 4.8600E+00 3.0000E-01 21734 19 29 1.4100E+02 4.6500E+00 5.0000E-01 21734 19 30 ENDDATA 14 21734 19 31 ENDSUBENT 3 21734 1999999 SUBENT 21734020 810213 21734 20 1 BIB 4 13 21734 20 2 REACTION (90-TH-232(N,F)MASS,CHN,FY) ABSOLUTE CHAIN YIELDS. 21734 20 3 ANALYSIS .IN THE ABSENCE OF KNOWN FRACTIONAL CUMULATIVE YIELDS 21734 20 4 THE EXPERIMENTAL AP VALUES WERE USED TO DERIVE ZP 21734 20 5 VALUES. ASSUMING THE SAME VARIATION OF ZP WITH A AS 21734 20 6 FOR THERMAL FISSION, AND A GAUSSIAN DISTRIBUTION 21734 20 7 FOR INDEPENDENT YIELDS, THE FRACTIONAL CUMULATIVE 21734 20 8 YIELDS WERE ESTIMATED. 21734 20 9 .NORMALISATION FACTORS ARE THE WEIGHTED AVERAGES OF 21734 20 10 RATIOS BETWEEN THE RELATIVE YIELDS AND ABSOLUTE VALUE 21734 20 11 GIVEN BY VON GUNTEN IN ACTINIDES REV 1,275,(1969). 21734 20 12 STATUS .TABLE 4B, COLUMN 4. 21734 20 13 HISTORY (810127C) 21734 20 14 (810213E) 21734 20 15 ENDBIB 13 21734 20 16 NOCOMMON 0 0 21734 20 17 DATA 3 11 21734 20 18 MASS DATA DATA-APRX 21734 20 19 NO-DIM PC/FIS PC/FIS 21734 20 20 8.7000E+01 4.7500E+00 21734 20 21 8.8000E+01 5.3200E+00 21734 20 22 8.9000E+01 5.6400E+00 21734 20 23 9.0000E+01 5.8200E+00 21734 20 24 9.1000E+01 5.8800E+00 21734 20 25 9.2000E+01 6.2000E+00 21734 20 26 1.3700E+02 4.8400E+00 21734 20 27 1.3800E+02 4.8800E+00 21734 20 28 1.3900E+02 5.5200E+00 21734 20 29 1.4000E+02 6.3400E+00 21734 20 30 1.4100E+02 5.2000E+00 21734 20 31 ENDDATA 13 21734 20 32 ENDSUBENT 3 21734 2099999 SUBENT 21734021 810213 21734 21 1 BIB 4 13 21734 21 2 REACTION (92-U-233(N,F)MASS,CHN,FY) ABSOLUTE CHAIN YIELDS. 21734 21 3 ANALYSIS .IN THE ABSENCE OF MEASURED FRACTIONAL CUMULATIVE 21734 21 4 YIELDS, VALUES ARE ESTIMATED FROM THE EXPERIMENTAL 21734 21 5 VALUES OF AP, FROM WHICH ZP VALUES ARE DERIVED. 21734 21 6 IT IS ASSUMED THAT ZP VARIES WITH A AS FOR THERMAL 21734 21 7 FISSION, AND THAT INDEPENDENT YIELDS FOLLOW A 21734 21 8 GAUSSIAN DISTRIBUTION IN Z. 21734 21 9 .NORMALISATION FACTORS ARE THE WEIGHTED AVERAGES OF 21734 21 10 RATIOS BETWEEN THE RELATIVE YIELDS AND ABSOLUTE 21734 21 11 VALUES FROM BORDEN AND KURODA, JIN,31,2623,(1968). 21734 21 12 STATUS .TABLE 4B, COLUMN 4. 21734 21 13 HISTORY (810127C) 21734 21 14 (810213E) 21734 21 15 ENDBIB 13 21734 21 16 NOCOMMON 0 0 21734 21 17 DATA 2 5 21734 21 18 MASS DATA 21734 21 19 NO-DIM PC/FIS 21734 21 20 8.7000E+01 4.0000E+00 21734 21 21 8.8000E+01 4.5000E+00 21734 21 22 8.9000E+01 5.4000E+00 21734 21 23 9.0000E+01 5.6000E+00 21734 21 24 9.1000E+01 5.8000E+00 21734 21 25 ENDDATA 7 21734 21 26 ENDSUBENT 2 21734 2199999 SUBENT 21734026 810723 21734 26 1 BIB 4 8 21734 26 2 REACTION (90-TH-232(N,F)ELEM,CHG,FY) ELEMENTARY YIELDS. 21734 26 3 ANALYSIS .THE SUM OF THE ABSOLUTE INDEPENDENT YIELDS FOR 21734 26 4 EACH ELEMENT. 21734 26 5 STATUS .TABLE 5. 21734 26 6 (DEP,21734002) 21734 26 7 (DEP,21734003) 21734 26 8 HISTORY (810127C) 21734 26 9 (810213E) 21734 26 10 ENDBIB 8 21734 26 11 NOCOMMON 0 0 21734 26 12 DATA 3 2 21734 26 13 ELEMENT DATA DATA-ERR 21734 26 14 NO-DIM PC/FIS PC/FIS 21734 26 15 3.6000E+01 1.5500E+01 1.2000E+00 21734 26 16 5.4000E+01 1.5200E+01 1.4000E+00 21734 26 17 ENDDATA 4 21734 26 18 ENDSUBENT 3 21734 2699999 SUBENT 21734027 810723 21734 27 1 BIB 4 8 21734 27 2 REACTION (92-U-233(N,F)ELEM,CHG,FY) ELEMENTARY YIELDS. 21734 27 3 ANALYSIS .THE SUM OF THE ABSOLUTE INDEPENDENT YIELDS FOR 21734 27 4 EACH ELEMENT. 21734 27 5 STATUS .TABLE 5. 21734 27 6 (DEP,21734004) 21734 27 7 (DEP,21734005) 21734 27 8 HISTORY (810127C) 21734 27 9 (810213E) 21734 27 10 ENDBIB 8 21734 27 11 NOCOMMON 0 0 21734 27 12 DATA 3 2 21734 27 13 ELEMENT DATA DATA-ERR 21734 27 14 NO-DIM PC/FIS PC/FIS 21734 27 15 3.6000E+01 1.2500E+01 1.4000E+00 21734 27 16 5.4000E+01 1.5400E+01 1.5000E+00 21734 27 17 ENDDATA 4 21734 27 18 ENDSUBENT 3 21734 2799999 SUBENT 21734028 810723 21734 28 1 BIB 4 8 21734 28 2 REACTION (92-U-235(N,F)ELEM,CHG,FY) ELEMENTARY YIELDS. 21734 28 3 ANALYSIS .THE SUM OF THE ABSOLUTE INDEPENDENT YIELDS FOR 21734 28 4 EACH ELEMENT. 21734 28 5 STATUS .TABLE 5. 21734 28 6 (DEP,21734006) 21734 28 7 (DEP,21734007) 21734 28 8 HISTORY (810127C) 21734 28 9 (810213E) 21734 28 10 ENDBIB 8 21734 28 11 NOCOMMON 0 0 21734 28 12 DATA 3 2 21734 28 13 ELEMENT DATA DATA-ERR 21734 28 14 NO-DIM PC/FIS PC/FIS 21734 28 15 3.6000E+01 9.8000E+00 1.0000E+00 21734 28 16 5.4000E+01 1.3500E+01 1.3000E+00 21734 28 17 ENDDATA 4 21734 28 18 ENDSUBENT 3 21734 2899999 SUBENT 21734029 810213 21734 29 1 BIB 4 6 21734 29 2 REACTION (92-U-238(N,F)ELEM,CHG,FY) ELEMENTARY YIELDS. 21734 29 3 ANALYSIS .THE SUM OF THE ABSOLUTE INDEPENDENT YIELDS FOR 21734 29 4 EACH ELEMENT. 21734 29 5 STATUS .TABLE 5. 21734 29 6 HISTORY (810127C) 21734 29 7 (810213E) 21734 29 8 ENDBIB 6 21734 29 9 NOCOMMON 0 0 21734 29 10 DATA 3 2 21734 29 11 ELEMENT DATA DATA-ERR 21734 29 12 NO-DIM PC/FIS PC/FIS 21734 29 13 3.6000E+01 9.0000E+00 9.0000E-01 21734 29 14 5.4000E+01 1.3100E+01 1.0000E+00 21734 29 15 ENDDATA 4 21734 29 16 ENDSUBENT 3 21734 2999999 ENDENTRY 25 2173499999999 ENTRY 21983 860904 21983 0 1 SUBENT 21983001 860703 21983 1 1 BIB 14 34 21983 1 2 INSTITUTE (2GERMUN) 21983 1 3 REFERENCE (J,PR/C,30,934,8409) 21983 1 4 AUTHOR (I.WINKELMANN,D.C.AUMANN) 21983 1 5 TITLE -FISSION OF PU-242 WITH 15.1 MEV NEUTRONS 21983 1 6 FACILITY (LINAC) 21983 1 7 INC-SOURCE (D-T) 900 KEV DEUTERONS ON A TRITIUM TARGET 21983 1 8 SAMPLE .PU-O(2)SAMPLE ISOTOPIC COMPOSITION 21983 1 9 PU-238 0.003 PERCENT 21983 1 10 PU-239 0.018 PERCENT 21983 1 11 PU-240 0.083 PERCENT 21983 1 12 PU-241 0.096 PERCENT 21983 1 13 PU-242 99.800 PERCENT 21983 1 14 PU-244 0.0005 PERCENT 21983 1 15 METHOD (CHSEP) FOR SOME FISSION PRODUCT ELEMENTS PD,AG,CD,SN, 21983 1 16 SB,CE FOLLOWED BY BETA COUNTING AND GAMMA RAY 21983 1 17 SPECTROMETRY 21983 1 18 DETECTOR (GELI) GE(LI) DETECTOR FOR GAMMA RAY SPECTROSCOPY 21983 1 19 MONITOR (29-CU-65(N,2N)29-CU-64,,SIG) 21983 1 20 (79-AU-197(N,2N)79-AU-196,,SIG) 21983 1 21 THESE TWO MONITORS WERE USED FOR THE FAST NEUTRON 21983 1 22 FLUENCE 21983 1 23 (79-AU-197(N,G)79-AU-198,,SIG) FOR THE THERMAL NEUTRON21983 1 24 FLUENCE. 0.01 PERCENT OF THE INTENSITY OF THE FAST 21983 1 25 NEUTRON FLUX 21983 1 26 ERR-ANALYS .SYSTEMATIC ERROR IN THE YIELD DETERMINATION NOT 21983 1 27 INCLUDED +-2 PERCENT) 21983 1 28 ADD-RES .PEAK TO VALLEY RATIO IN THE MASS YIELD DISTRIBUTION IS21983 1 29 ABOUT 9.5.THE AVERAGE MASSES OF THE LIGHT AND HEAVY 21983 1 30 GROUPS ARE 101.5 AND 136.5 RESPECTIVELY. 21983 1 31 STATUS .TAKEN FROM MAIN REFERENCE 21983 1 32 HISTORY (851106C) IF. 21983 1 33 (860210E) 21983 1 34 (860430A) 21983 1 35 (860703E) 21983 1 36 ENDBIB 34 21983 1 37 COMMON 6 3 21983 1 38 EN EN-RSL MONIT1 MONIT1-ERR MONIT2 MONIT2-ERR 21983 1 39 MEV MEV MB MB MB MB 21983 1 40 1.5100E+01 7.0000E-01 9.7500E+02 5.0000E+01 2.2500E+03 1.2000E+0221983 1 41 ENDCOMMON 6 3 21983 1 42 ENDSUBENT 6 21983 199999 SUBENT 21983002 860703 21983 2 1 BIB 4 83 21983 2 2 REACTION (94-PU-242(N,F)ELEM/MASS,CUM,FY) 21983 2 3 DECAY-DATA ((1.)36-KR-85-M,4.48HR,DG,151.2,0.746) 21983 2 4 ((2.)36-KR-87,1.27HR,DG,402.6,0.494) 21983 2 5 ((3.)36-KR-88,2.80HR,DG,196.3,0.263) 21983 2 6 ((4.)37-RB-89,15.15MIN,DG,1031.9,0.636,DG,1248.1,0.467)21983 2 7 ((5.)38-SR-91,9.48HR,DG,749.7,0.244,DG,1024.3,0.340) 21983 2 8 ((6.)39-Y-91-M,0.828HR,DG,555.6,0.560) 21983 2 9 ((7.)38-SR-92,2.71HR,DG,1383.9,0.90) 21983 2 10 ((8.)39-Y-92,3.53HR,DG,934.5,0.138) 21983 2 11 ((9.)39-Y-93,10.10HR,DG,266.9,0.0695) 21983 2 12 ((10.)39-Y-94,18.70MIN,DG,919.2,0.49) 21983 2 13 ((11.)40-ZR-95,63.98D,DG,724.3,0.444,DG,756.7,0.546) 21983 2 14 ((12.)40-ZR-97,17.00HR,DG,743.4,0.946) 21983 2 15 ((13.)41-NB-97-G,1.20HR,DG,657.9,0.983) 21983 2 16 ((14.)42-MO-99,66.02HR,DG,181.9,0.060,DG,739.5,0.123) 21983 2 17 ((15.)43-TC-99-M,6.01HR,DG,140.5,0.825) 21983 2 18 ((16.)43-TC-101,14.2MIN,DG,306.9,0.886) 21983 2 19 ((17.)44-RU-103,39.35D,DG,497.1,0.894) 21983 2 20 ((18.)43-TC-104,18.20MIN,DG,358.0,0.903,DG,535.1,0.134)21983 2 21 ((19.)44-RU-105,4.40HR,DG,316.4,0.111,DG,469.4,0.175, 21983 2 22 DG,676.4,0.157,DG,724.2,0.473) 21983 2 23 ((20.)45-RH-105,35.36HR,DG,318.9,0.192) 21983 2 24 ((21.)45-RH-107,21.70MIN,DG,302.8,0.659) 21983 2 25 ((22.)46-PD-109,13.46HR,DG,88.0,0.0389) 21983 2 26 ((23.)46-PD-111-M,5.50HR,DG,172.0,0.324) 21983 2 27 ((24.)47-AG-111-G,7.43D,DG,342.1,0.0668) 21983 2 28 ((25.)46-PD-112,20.12HR,DG,616.8,0.433)EMITTED BY THE 21983 2 29 DAUGHTER IN EQUILIBRIUM 21983 2 30 ((26.)47-AG-113-G,5.37HR,DG,298.0,0.0830) 21983 2 31 ((27.)48-CD-115-G,2.21D,DG,527.7,0.267) 21983 2 32 ((28.)49-IN-115-M,4.3HR,DG,336.2,0.482) 21983 2 33 ((29.)48-CD-117-M,3.35HR,DG,564.4,0.153,DG,1066.0,0.23)21983 2 34 ((30.)48-CD-117-G,2.56HR,DG,273.3,0.284,DG,344.5,0.173,21983 2 35 DG,1303.4,0.176) 21983 2 36 ((31.)48-CD-118,0.838HR,DG,1229.5,0.15) 21983 2 37 ((32.)50-SN-125-G,9.64D,DG,1066.6,0.886) 21983 2 38 ((33.)51-SB-125,2.77YR,DG,427.9,0.297) 21983 2 39 ((34.)51-SB-126-G,12.40D,DG,414.8,0.88,DG,666.3,1.00, 21983 2 40 DG,695.0,1.00) 21983 2 41 ((35.)50-SN-127-G,2.10HR,DG,1095.6,0.15,DG,1114.3,0.29)21983 2 42 ((36.)51-SB-127,3.85D,DG,473.0,0.250,DG,685.7,0.357, 21983 2 43 DG,783.5,0.147) 21983 2 44 ((37.)50-SN-128,0.985HR,DG,482.3,0.58) 21983 2 45 ((38.)51-SB-128-M,10.0MIN,DG,753.9,1.00) 21983 2 46 ((39.)51-SB-128-G,9.10HR,DG,754.0,1.00) 21983 2 47 ((40.)51-SB-129,4.32HR,DG,812.6,0.435,DG,914.7,0.188, 21983 2 48 DG,1030.4,0.124) 21983 2 49 ((41.)52-TE-129-G,1.16HR,DG,459.6,0.0714) 21983 2 50 ((42.)51-SB-130-G,0.667HR,DG,330.9,0.778,DG,793.4,0.99,21983 2 51 DG,839.4,0.998) 21983 2 52 ((43.)51-SB-131,23.0MIN,DG,943.6,0.440) 21983 2 53 ((44.)52-TE-131-M,1.25D,DG,793.8,0.138,DG,852.2,0.206, 21983 2 54 DG,1125.5,0.114,DG,1206.6,0.09)21983 2 55 ((45.)53-I-131,8.04D,DG,364.5,0.824) 21983 2 56 ((46.)52-TE-132,3.24D,DG,228.2,0.880) 21983 2 57 ((47.)53-I-132-G,2.30HR,DG,522.7,0.161,DG,630.2,0.137, 21983 2 58 DG,667.7,0.987,DG,772.6,0.762, 21983 2 59 DG,954.6,0.181) 21983 2 60 ((48.)52-TE-133-M,0.923HR,DG,647.7,0.293,DG,864.6,0.19,21983 2 61 DG,913.0,0.870) 21983 2 62 ((49.)53-I-133,20.80HR,DG,529.9,0.873) 21983 2 63 ((50.)54-XE-133,5.25D,DG,81.0,0.371) 21983 2 64 ((51.)53-I-134-G,0.877HR,DG,595.4,0.114,DG,847.0,0.954,21983 2 65 DG,884.1,0.653,DG,1072.6,0.15)21983 2 66 ((52.)53-I-135,6.70HR,DG,1131.6,0.230,DG,1260.5,0.303) 21983 2 67 ((53.)54-XE-135,9.15HR,DG,249.7,0.906) 21983 2 68 ((54.)55-CS-138-G,32.20MIN,DG,462.8,0.308, 21983 2 69 DG,1009.8,0.2,DG,1435.9,0.763) 21983 2 70 ((55.)56-BA-139,1.38HR,DG,165.9,0.188) 21983 2 71 ((56.)56-BA-140,12.79D,DG,537.3,0.240) 21983 2 72 ((57.)57-LA-140,40.20HR,DG,486.0,0.453,DG,1596.2,0.953)21983 2 73 ((58.)58-CE-141,32.45D,DG,145.4,0.481) 21983 2 74 ((59.)57-LA-142,1.55HR,DG,641.2,0.49) 21983 2 75 ((60.)58-CE-143,33.0HR,DG,293.3,0.434) 21983 2 76 ((61.)58-CE-144,284.6D,DG,133.5,0.111) 21983 2 77 ((62.)59-PR-146,24.20MIN,DG,453.6,0.55) 21983 2 78 ((63.)60-ND-149,1.73HR,DG,211.3,0.273,DG,423.6,0.0945) 21983 2 79 ((64.)61-PM-151,28.00HR,DG,340.1,0.224) 21983 2 80 STATUS .TAKEN FROM MAIN REFERENCE 21983 2 81 HISTORY (851105C) IF. 21983 2 82 (860210E) 21983 2 83 (860430A) MISC COLUMN ADDED 21983 2 84 (860703E) 21983 2 85 ENDBIB 83 21983 2 86 NOCOMMON 0 0 21983 2 87 DATA 7 65 21983 2 88 MASS ELEMENT ISOMER DECAY-FLAG DATA DATA-ERR 21983 2 89 DATA-MAX 21983 2 90 NO-DIM NO-DIM NO-DIM NO-DIM PC/FIS PER-CENT 21983 2 91 PC/FIS 21983 2 92 8.5000E+01 3.6000E+01 1.0000E+00 1.0000E+00 6.7200E-01 7.1000E+0021983 2 93 21983 2 94 8.7000E+01 3.6000E+01 2.0000E+00 9.9300E-01 7.6000E+0021983 2 95 21983 2 96 8.8000E+01 3.6000E+01 3.0000E+00 1.1600E+00 8.1000E+0021983 2 97 21983 2 98 8.9000E+01 3.7000E+01 4.0000E+00 1.3300E+00 1.1000E+0121983 2 99 21983 2 100 9.1000E+01 3.8000E+01 5.0000E+00 2.1100E+00 7.1000E+0021983 2 101 21983 2 102 9.1000E+01 3.9000E+01 1.0000E+00 6.0000E+00 2.0300E+00 7.9000E+0021983 2 103 21983 2 104 9.2000E+01 3.8000E+01 7.0000E+00 2.2600E+00 1.3000E+0121983 2 105 21983 2 106 9.2000E+01 3.9000E+01 8.0000E+00 2.4900E+00 1.2000E+0121983 2 107 21983 2 108 9.3000E+01 3.9000E+01 9.0000E+00 2.6000E+00 1.3000E+0121983 2 109 21983 2 110 9.4000E+01 3.9000E+01 1.0000E+01 2.7900E+00 1.0000E+0121983 2 111 21983 2 112 9.5000E+01 4.0000E+01 1.1000E+01 3.3700E+00 8.9000E+0021983 2 113 21983 2 114 9.7000E+01 4.0000E+01 1.2000E+01 4.2300E+00 7.5000E+0021983 2 115 21983 2 116 9.7000E+01 4.1000E+01 1.3000E+01 4.2200E+00 7.1000E+0021983 2 117 21983 2 118 9.9000E+01 4.2000E+01 1.4000E+01 4.9700E+00 7.2000E+0021983 2 119 21983 2 120 9.9000E+01 4.3000E+01 1.0000E+00 1.5000E+01 4.7000E+00 7.4000E+0021983 2 121 21983 2 122 1.0100E+02 4.3000E+01 1.6000E+01 5.0400E+00 9.9000E+0121983 2 123 21983 2 124 1.0300E+02 4.4000E+01 1.7000E+01 5.6400E+00 7.9000E+0121983 2 125 21983 2 126 1.0400E+02 4.3000E+01 1.8000E+01 5.4500E+00 1.2000E+0121983 2 127 21983 2 128 1.0500E+02 4.4000E+01 1.9000E+01 5.5800E+00 7.5000E+0021983 2 129 21983 2 130 1.0500E+02 4.5000E+01 2.0000E+01 5.4200E+00 7.9000E+0021983 2 131 21983 2 132 1.0700E+02 4.5000E+01 2.1000E+01 3.8000E+00 1.0000E+0121983 2 133 21983 2 134 1.0900E+02 4.6000E+01 2.2000E+01 2.5300E+00 8.6000E+0021983 2 135 21983 2 136 1.1100E+02 4.6000E+01 1.0000E+00 2.3000E+01 9.4000E-05 6.4000E+0121983 2 137 21983 2 138 1.1100E+02 4.7000E+01 2.4000E+01 2.2000E+00 1.1000E+0121983 2 139 21983 2 140 1.1200E+02 4.6000E+01 2.5000E+01 1.9200E+00 7.2000E+0021983 2 141 21983 2 142 1.1300E+02 4.7000E+01 0.0000E+00 2.6000E+01 1.6000E+00 1.0000E+0121983 2 143 21983 2 144 1.1500E+02 4.8000E+01 1.0000E+00 2.7000E+01 3.5000E+0121983 2 145 1.1000E-01 21983 2 146 1.1500E+02 4.8000E+01 0.0000E+00 2.8000E+01 1.1200E+00 1.3000E+0121983 2 147 21983 2 148 1.1700E+02 4.8000E+01 1.0000E+00 2.9000E+01 1.5100E-01 2.0000E+0121983 2 149 21983 2 150 1.1700E+02 4.8000E+01 0.0000E+00 3.0000E+01 5.0300E-01 2.0000E+0121983 2 151 21983 2 152 1.1800E+02 4.8000E+01 3.1000E+01 4.2000E-01 1.6000E+0121983 2 153 21983 2 154 1.2100E+02 5.0000E+01 0.0000E+00 6.5800E-01 2.0000E+0121983 2 155 21983 2 156 1.2500E+02 5.0000E+01 0.0000E+00 3.2000E+01 6.8400E-01 1.6000E+0121983 2 157 21983 2 158 1.2500E+02 5.1000E+01 3.3000E+01 1.3500E+00 1.8000E+0121983 2 159 21983 2 160 1.2600E+02 5.1000E+01 0.0000E+00 3.4000E+01 1.2000E-01 6.0000E+0121983 2 161 21983 2 162 1.2700E+02 5.0000E+01 0.0000E+00 3.5000E+01 1.6600E+00 1.1000E+0121983 2 163 21983 2 164 1.2700E+02 5.1000E+01 3.6000E+01 1.8700E+00 1.1200E+0121983 2 165 21983 2 166 1.2800E+02 5.0000E+01 3.7000E+01 1.3000E+00 1.7000E+0121983 2 167 21983 2 168 1.2800E+02 5.1000E+01 1.0000E+00 3.8000E+01 1.2900E+00 2.0000E+0121983 2 169 21983 2 170 1.2800E+02 5.1000E+01 0.0000E+00 3.9000E+01 6.7800E-01 1.1000E+0121983 2 171 21983 2 172 1.2900E+02 5.1000E+01 4.0000E+01 2.0000E+00 1.0000E+0121983 2 173 21983 2 174 1.2900E+02 5.2000E+01 4.1000E+01 2.1600E+00 1.0000E+0121983 2 175 21983 2 176 1.3000E+02 5.1000E+01 0.0000E+00 4.2000E+01 1.4200E+00 1.2000E+0121983 2 177 21983 2 178 1.3100E+02 5.1000E+01 4.3000E+01 2.4000E+00 1.3000E+0121983 2 179 21983 2 180 1.3100E+02 5.2000E+01 1.0000E+00 4.4000E+01 1.5900E+00 1.0000E+0121983 2 181 21983 2 182 1.3100E+02 5.3000E+01 4.5000E+01 3.9100E+00 6.1000E+0021983 2 183 21983 2 184 1.3200E+02 5.2000E+01 4.6000E+01 4.5600E+00 7.4000E+0021983 2 185 21983 2 186 1.3200E+02 5.3000E+01 4.7000E+01 5.2700E+00 5.3000E+0021983 2 187 21983 2 188 1.3300E+02 5.2000E+01 1.0000E+00 4.8000E+01 1.4300E+00 1.3000E+0121983 2 189 21983 2 190 1.3300E+02 5.3000E+01 4.9000E+01 5.5200E+01 7.2000E+0021983 2 191 21983 2 192 1.3300E+02 5.4000E+01 5.0000E+01 5.6600E+01 7.6000E+0021983 2 193 21983 2 194 1.3400E+02 5.3000E+01 5.1000E+01 5.9900E+01 1.2000E+0121983 2 195 21983 2 196 1.3500E+02 5.3000E+01 5.2000E+01 5.1000E+01 8.7000E+0021983 2 197 21983 2 198 1.3500E+02 5.4000E+01 5.3000E+01 5.5200E+01 8.9000E+0021983 2 199 21983 2 200 1.3800E+02 5.5000E+01 5.4000E+01 5.0000E+01 9.1000E+0021983 2 201 21983 2 202 1.3900E+02 5.6000E+01 5.5000E+01 4.9300E+01 7.7000E+0021983 2 203 21983 2 204 1.4000E+02 5.6000E+01 5.6000E+01 4.8400E+01 9.0000E+0021983 2 205 21983 2 206 1.4000E+02 5.7000E+01 5.7000E+01 4.9500E+01 7.8000E+0021983 2 207 21983 2 208 1.4100E+02 5.8000E+01 5.8000E+01 4.8600E+01 8.2000E+0021983 2 209 21983 2 210 1.4200E+02 5.7000E+01 5.9000E+01 4.3400E+01 7.6000E+0021983 2 211 21983 2 212 1.4300E+02 5.8000E+01 6.0000E+01 3.6600E+01 7.1000E+0021983 2 213 21983 2 214 1.4400E+02 5.8000E+01 6.1000E+01 3.1900E+01 8.4000E+0021983 2 215 21983 2 216 1.4600E+02 5.9000E+01 6.2000E+01 2.1800E+01 8.7000E+0021983 2 217 21983 2 218 1.4900E+02 6.0000E+01 6.3000E+01 1.6100E+01 9.9000E+0021983 2 219 21983 2 220 1.5100E+02 6.1000E+01 6.4000E+01 9.1500E+01 9.7000E+0021983 2 221 21983 2 222 ENDDATA 134 21983 2 223 ENDSUBENT 7 21983 299999 SUBENT 21983003 860904 21983 3 1 BIB 5 18 21983 3 2 REACTION (94-PU-242(N,F)ELEM/MASS,CHN,FY) 21983 3 3 MISC-COL .ESTIMATED FRACTION OF TOTAL CHAUN YIELD 21983 3 4 FLAG (1.) BRANCHING RATIO OF THE BETA DECAY OF THE PRECURSOR21983 3 5 ALREADY TAKEN INTO ACCOUNT 21983 3 6 (2.) PARTIAL ISOMERIC YIELD ONLY 21983 3 7 (3.) TOTAL CHAIN YIELD CALCULATED USING THE BRANCHING 21983 3 8 RATIO OF 0.90 FOR THE BETA DECAY OF THE PRECURSOR 21983 3 9 (4.) TOTAL CHAIN YIELD CALCULATED USING A CUMULATIVE 21983 3 10 ISOMER RATIO OF SN 121M /SN 121G =0.16+-0.01 21983 3 11 (5.) FISSION YIELD DETERMINED BY MEASURING SN128 DIRECT21983 3 12 (6.) FISSION YIELD OF SN128 DETERMINED BY MEASUREMENT 21983 3 13 (7.) INDEPENDANT FISSION YIELD 21983 3 14 OF ITS DAUGHTER SB128M. 21983 3 15 STATUS .TAKEN FROM MAIN REFERENCE. 21983 3 16 HISTORY (851120C) IF. 21983 3 17 (860210E) 21983 3 18 (860620A) DATA HEADING AND FLAGS REORGANIZED 21983 3 19 (860703E) 21983 3 20 ENDBIB 18 21983 3 21 NOCOMMON 0 0 21983 3 22 DATA 7 80 21983 3 23 MASS DATA DATA-ERR FLAG MISC MISC-ERR 21983 3 24 DATA-MAX 21983 3 25 NO-DIM PC/FIS PC/FIS NO-DIM NO-DIM NO-DIM 21983 3 26 PC/FIS 21983 3 27 8.5000E+01 6.7200E-01 4.8000E-02 1.0000E+00 21983 3 28 21983 3 29 8.7000E+01 9.9500E-01 7.6000E-02 9.9800E-01 1.0000E-0321983 3 30 21983 3 31 8.8000E+01 1.1800E+00 1.0000E-01 9.8100E-01 7.0000E-0321983 3 32 21983 3 33 8.9000E+01 1.3300E+00 1.5000E-01 9.9900E-01 1.0000E-0321983 3 34 21983 3 35 9.1000E+01 2.1100E+00 1.5000E-01 1.0000E+00 21983 3 36 21983 3 37 9.1000E+01 2.0300E+00 1.6000E-01 1.0000E+00 1.0000E+00 21983 3 38 21983 3 39 9.1000E+01 2.0700E+00 1.1000E-01 21983 3 40 21983 3 41 9.2000E+01 2.2700E+00 3.0000E-01 9.9800E-01 1.0000E-0321983 3 42 21983 3 43 9.2000E+01 2.4900E+00 3.0000E-01 1.0000E+00 21983 3 44 21983 3 45 9.2000E+01 2.3800E+00 2.1000E-01 21983 3 46 21983 3 47 9.3000E+01 2.6000E+00 3.4000E-01 1.0000E+00 21983 3 48 21983 3 49 9.4000E+01 2.8000E+00 2.8000E-01 9.9900E-01 1.0000E-0321983 3 50 21983 3 51 9.5000E+01 3.3700E+00 3.0000E-01 1.0000E+00 21983 3 52 21983 3 53 9.7000E+01 4.2400E+00 3.2000E-01 9.9800E-01 1.0000E-0321983 3 54 21983 3 55 9.7000E+01 4.2200E+00 3.0000E-01 1.0000E+00 21983 3 56 21983 3 57 9.7000E+01 4.2300E+00 2.2000E-01 21983 3 58 21983 3 59 9.9000E+01 4.9700E+00 3.6000E-01 1.0000E+00 21983 3 60 21983 3 61 9.9000E+01 4.7000E+00 3.5000E-01 1.0000E+00 1.0000E+00 21983 3 62 21983 3 63 9.9000E+01 4.8400E+00 2.5000E-01 21983 3 64 21983 3 65 1.0100E+02 5.0400E+00 5.0000E-01 1.0000E+00 21983 3 66 21983 3 67 1.0300E+02 5.6400E+00 4.5000E-01 1.0000E+00 21983 3 68 21983 3 69 1.0400E+02 5.4500E+00 6.6000E-01 1.0000E+00 21983 3 70 21983 3 71 1.0500E+02 5.5800E+00 4.2000E-01 1.0000E+00 21983 3 72 21983 3 73 1.0500E+02 5.4200E+00 4.3000E-01 1.0000E+00 21983 3 74 21983 3 75 1.0500E+02 5.5000E+00 3.0000E-01 21983 3 76 21983 3 77 1.0700E+02 3.8000E+00 3.8000E-01 1.0000E+00 21983 3 78 21983 3 79 1.0900E+02 2.5300E+00 2.2000E-01 1.0000E+00 21983 3 80 21983 3 81 1.1100E+02 9.4000E-03 6.0000E-03 2.0000E+00 1.0000E+00 21983 3 82 21983 3 83 1.1100E+02 2.2000E+00 2.4000E-01 1.0000E+00 21983 3 84 21983 3 85 1.1200E+02 1.9200E+00 1.4000E-01 9.9800E-01 2.0000E-0321983 3 86 21983 3 87 1.1300E+02 1.6000E+00 1.6000E-01 1.0000E+00 21983 3 88 21983 3 89 1.1300E+02 1.7800E+00 2.5000E-01 3.0000E+00 21983 3 90 21983 3 91 1.1500E+02 4.0000E-02 1.0000E+00 21983 3 92 1.1000E+01 21983 3 93 1.1500E+02 1.1200E+00 1.5000E-01 1.0000E+00 21983 3 94 21983 3 95 1.1500E+02 1.6000E-01 21983 3 96 1.2300E+00 21983 3 97 1.1700E+02 1.5000E-01 3.0000E-02 9.9990E-01 1.0000E-0321983 3 98 21983 3 99 1.1700E+02 5.0000E-01 1.0000E-01 9.9990E-01 1.0000E-0321983 3 100 21983 3 101 1.1700E+02 6.5000E-01 1.1000E-01 21983 3 102 21983 3 103 1.1800E+02 4.2000E-01 7.0000E-02 9.9600E-01 6.0000E-0321983 3 104 21983 3 105 1.2100E+02 6.6000E-01 1.3000E-01 1.0000E+00 21983 3 106 21983 3 107 1.2100E+02 7.6000E-01 1.7000E-01 4.0000E+00 21983 3 108 21983 3 109 1.2500E+02 6.9000E-01 1.1000E-01 2.0000E+00 9.9000E-01 9.0000E-0321983 3 110 21983 3 111 1.2500E+02 1.3500E+00 2.4000E-01 1.0000E+00 21983 3 112 21983 3 113 1.2600E+02 1.2000E-01 7.0000E-02 7.0000E+00 21983 3 114 21983 3 115 1.2700E+02 1.8800E+00 2.3000E-01 8.8600E-01 5.0000E-0221983 3 116 21983 3 117 1.2700E+02 1.8700E+00 2.2000E-01 9.9900E-01 2.0000E-0321983 3 118 21983 3 119 1.2800E+02 3.1000E-01 5.0000E+00 7.5900E-01 5.0000E-0221983 3 120 21983 3 121 1.2800E+02 1.7000E+00 3.6000E-01 6.0000E+00 7.5900E-01 5.0000E-0221983 3 122 21983 3 123 1.2800E+02 1.7100E+00 2.4000E-01 21983 3 124 21983 3 125 1.2800E+02 6.8000E-01 8.0000E-02 2.0000E+00 9.9400E-01 3.0000E-0321983 3 126 21983 3 127 1.2900E+02 2.0700E+00 2.1000E-01 9.6700E-01 1.1000E-0221983 3 128 21983 3 129 1.2900E+02 2.1600E+00 2.2000E-01 1.0000E+00 1.0000E+00 21983 3 130 21983 3 131 1.2900E+02 2.1100E+00 1.6000E-01 21983 3 132 21983 3 133 1.3000E+02 1.6100E+00 2.0000E-01 8.8100E-01 2.9000E-0221983 3 134 21983 3 135 1.3100E+02 3.5500E+00 5.3000E-01 6.7600E-01 5.1000E-0221983 3 136 21983 3 137 1.3100E+02 1.6100E+00 1.6000E-01 9.8700E-01 5.0000E-0321983 3 138 21983 3 139 1.3100E+02 3.9100E+00 2.4000E-01 1.0000E+00 21983 3 140 21983 3 141 1.3200E+02 4.8800E+00 3.7000E-01 9.3500E-01 1.8000E-0221983 3 142 21983 3 143 1.3200E+02 5.2700E+00 2.8000E-01 1.0000E+00 21983 3 144 21983 3 145 1.3200E+02 5.1300E+00 2.3000E-01 21983 3 146 21983 3 147 1.3300E+02 1.8300E+00 2.6000E-01 2.0000E+00 7.7900E-01 3.8000E-0221983 3 148 21983 3 149 1.3300E+02 5.5400E+00 4.0000E-01 9.9500E-01 3.0000E-0321983 3 150 21983 3 151 1.3300E+02 5.6600E+00 4.3000E-01 1.0000E+00 21983 3 152 21983 3 153 1.3300E+02 5.6000E+00 3.0000E-01 21983 3 154 21983 3 155 1.3400E+02 5.8300E+00 7.0000E-01 9.6000E-01 1.2000E-0221983 3 156 21983 3 157 1.3500E+02 6.0100E+00 5.7000E-01 8.4800E-01 3.2000E-0221983 3 158 21983 3 159 1.3500E+02 5.5300E+00 4.9000E-01 9.9800E-01 1.0000E-0321983 3 160 21983 3 161 1.3500E+02 5.7500E+00 3.8000E-01 21983 3 162 21983 3 163 1.3800E+02 5.0200E+00 4.6000E-01 9.9600E-01 1.6000E-0221983 3 164 21983 3 165 1.3900E+02 4.9300E+00 3.8000E-01 1.0000E+00 21983 3 166 21983 3 167 1.4000E+02 4.8500E+00 4.4000E-01 9.9900E-01 1.0000E-0321983 3 168 21983 3 169 1.4000E+02 4.9500E+00 3.9000E-01 1.0000E+00 21983 3 170 21983 3 171 1.4000E+02 4.9100E+00 3.0000E-01 21983 3 172 21983 3 173 1.4100E+02 4.8600E+00 4.0000E-01 1.0000E+00 21983 3 174 21983 3 175 1.4200E+02 4.3400E+00 3.3000E-01 1.0000E+00 21983 3 176 21983 3 177 1.4300E+02 3.6600E+00 2.6000E-01 1.0000E+00 21983 3 178 21983 3 179 1.4400E+02 3.1900E+00 2.7000E-01 1.0000E+00 21983 3 180 21983 3 181 1.4600E+02 2.1800E+00 1.9000E-01 1.0000E+00 21983 3 182 21983 3 183 1.4900E+02 1.6100E+00 1.6000E-01 1.0000E+00 21983 3 184 21983 3 185 1.5100E+02 9.2000E-01 9.0000E-02 1.0000E+00 21983 3 186 21983 3 187 ENDDATA 164 21983 3 188 ENDSUBENT 7 21983 399999 ENDENTRY 3 2198399999999 ENTRY 22038 890207 22038 0 1 SUBENT 22038001 890207 22038 1 1 BIB 14 32 22038 1 2 INSTITUTE (2GERMNZ) EXPERIMENTAL SITE. 22038 1 3 (1USAUSA) TELEDYNE ISOTOPES, WESTWOOD, NEW 22038 1 4 JERSEY. P.A. 22038 1 5 REFERENCE (J,NP/A,198,228,7212) 22038 1 6 AUTHOR (P.ALEXANDER) 22038 1 7 TITLE -INDEPENDENT YIELDS OF XE-133,135 IN THE FISSION OF 22038 1 8 U-235,238 AND PU-239 BY 14 MEV NEUTRONS. 22038 1 9 FACILITY (CCW ) COCKROFT-WALTON ACCELERATOR AT THE GUTENBERG 22038 1 10 UNIVERSITY IN MAINZ. 22038 1 11 INC-SOURCE (D-T ) A DEUTERON BEAM CURRENT OF 4 MILLI-A AT 550 22038 1 12 KEV PRODUCED A 14 MEV NEUTRON FLUX OF 1.5E+11 22038 1 13 NEUTRONS/CM2 ON TARGET. THE SAMPLES WAS LOCATED 22038 1 14 5 MM FROM THE TRITIUM TARGET. IRRADIATION TIME 22038 1 15 BETWEEN 1 AND 8 MIN. 22038 1 16 METHOD (CHSEP) THE XE GAS FISSION PRODUCTS WERE SEPARATED 22038 1 17 BY MEANS OF FAST CHEMISTRY BEFORE GAMMA COUNTING. 22038 1 18 DETECTOR (GELI ) TWO DIFFERENT GE-LI DETECTORS WERE USED FOR 22038 1 19 GAMMA SPECTROSCOPY OF THE XE FISSION PRODUCTS. 22038 1 20 PART-DET (DG ) 22038 1 21 ANALYSIS .WITH THE ISIS-2 FITTING PROGRAM,THE EXPERIMENTAL 22038 1 22 COUNTING DATA WERE ANALYSED.THE PROGRAM DETERMINES THE22038 1 23 PARAMETERS ZP AND W (THE FWHM VALUE) WHICH CHARACTE- 22038 1 24 RIZE THE GAUSSIAN CHARGE DISTRIBUTION 22038 1 25 CORRECTION .NO DETAILS GIVEN. 22038 1 26 ERR-ANALYS (DATA-ERR) ONLY RMS ERROR FOR REPEATED MEASUREMENTS. 22038 1 27 THE TOTAL ERRORS ARE ESTIMATED TO BE AT MINIMUM 10 TO 22038 1 28 30 PER-CENT. 22038 1 29 STATUS .DATA TAKEN FROM MAIN REFERENCE. 22038 1 30 HISTORY (871029C) N.O. 22038 1 31 (871210E) 22038 1 32 (880803U) IF. 22038 1 33 (880810E) 22038 1 34 ENDBIB 32 22038 1 35 NOCOMMON 0 0 22038 1 36 ENDSUBENT 0 22038 199999 SUBENT 22038002 890207 22038 2 1 BIB 4 13 22038 2 2 REACTION ((92-U-235(N,F)ELEM/MASS,IND,FY)/ 22038 2 3 (92-U-235(N,F)MASS,CHN,FY)) 22038 2 4 SAMPLE .MULTIPLY ENCAPSULATED FISSILE SAMPLES. THE ENCAPSU- 22038 2 5 LATION CONSISTED OF GAS-TIGHT GELATIN AND A 0.1 CM 22038 2 6 THICK CADMIUM SHIELD. TYPICAL COMPOSITIONS AND MASSES 22038 2 7 WERE 22038 2 8 U-235 0.5 MM THICK METAL FOIL, WEIGHT 300 MILLI-G,22038 2 9 ENRICHMENT 97.68 PER-CENT. 22038 2 10 STATUS .DATA TAKEN FROM MAIN REFERENCE. 22038 2 11 HISTORY (871029C) N.O. 22038 2 12 (871210E) 22038 2 13 (880803U) IF. 22038 2 14 (880810E) 22038 2 15 ENDBIB 13 22038 2 16 COMMON 1 3 22038 2 17 EN 22038 2 18 MEV 22038 2 19 1.4000E+01 22038 2 20 ENDCOMMON 1 3 22038 2 21 DATA 4 2 22038 2 22 ELEMENT MASS DATA DATA 22038 2 23 NO-DIM NO-DIM NO-DIM NO-DIM 22038 2 24 5.4000E+01 1.3300E+02 2.2000E-02 7.0000E-03 22038 2 25 5.4000E+01 1.3500E+02 2.6000E-01 1.0000E-02 22038 2 26 ENDDATA 4 22038 2 27 ENDSUBENT 4 22038 299999 SUBENT 22038003 890207 22038 3 1 BIB 4 13 22038 3 2 REACTION ((92-U-238(N,F)ELEM/MASS,IND,FY)/ 22038 3 3 (92-U-238(N,F)MASS,CHN,FY)) 22038 3 4 SAMPLE .MULTIPLY ENCAPSULATED FISSILE SAMPLES. THE ENCAPSU- 22038 3 5 LATION CONSISTED OF GAS-TIGHT GELATIN AND A 0.1 CM 22038 3 6 THICK CADMIUM SHIELD. TYPICAL COMPOSITIONS AND MASSES 22038 3 7 WERE 22038 3 8 U-238 0.25 MM THICK METAL FOIL, DEPLETED IN U-235 22038 3 9 TO 40 PPM, WEIGHT 200 MILLI-G. 22038 3 10 STATUS .DATA TAKEN FROM MAIN REFERENCE. 22038 3 11 HISTORY (871029C) N.O. 22038 3 12 (871210E) 22038 3 13 (880803U) IF. 22038 3 14 (880810E) 22038 3 15 ENDBIB 13 22038 3 16 COMMON 1 3 22038 3 17 EN 22038 3 18 MEV 22038 3 19 1.4000E+01 22038 3 20 ENDCOMMON 1 3 22038 3 21 DATA 4 2 22038 3 22 ELEMENT MASS DATA DATA 22038 3 23 NO-DIM NO-DIM NO-DIM NO-DIM 22038 3 24 5.4000E+01 1.3300E+02 3.0000E-03 1.3000E-03 22038 3 25 5.4000E+01 1.3500E+02 5.6000E-02 3.7000E-02 22038 3 26 ENDDATA 4 22038 3 27 ENDSUBENT 4 22038 399999 SUBENT 22038004 890207 22038 4 1 BIB 4 13 22038 4 2 REACTION ((94-PU-239(N,F)ELEM/MASS,IND,FY)/ 22038 4 3 (94-PU-239(N,F)MASS,CHN,FY)) 22038 4 4 SAMPLE .MULTIPLY ENCAPSULATED FISSILE SAMPLES. THE ENCAPSU- 22038 4 5 LATION CONSISTED OF GAS-TIGHT GELATIN AND A 0.1 CM 22038 4 6 THICK CADMIUM SHIELD. TYPICAL COMPOSITIONS AND MASSES 22038 4 7 WERE 22038 4 8 PU-239 STRIPS OF METAL, WEIGHT 20 MILLI-G, ENRICHED22038 4 9 TO 99.12 PER-CENT. 22038 4 10 STATUS .DATA TAKEN FROM MAIN REFERENCE. 22038 4 11 HISTORY (871029C) N.O. 22038 4 12 (871210E) 22038 4 13 (880803U) IF. 22038 4 14 (880810E) 22038 4 15 ENDBIB 13 22038 4 16 COMMON 1 3 22038 4 17 EN 22038 4 18 MEV 22038 4 19 1.4000E+01 22038 4 20 ENDCOMMON 1 3 22038 4 21 DATA 4 2 22038 4 22 ELEMENT MASS DATA DATA 22038 4 23 NO-DIM NO-DIM NO-DIM NO-DIM 22038 4 24 5.4000E+01 1.3300E+02 1.2000E-01 1.0000E-03 22038 4 25 5.4000E+01 1.3500E+02 4.6000E-01 3.0000E-02 22038 4 26 ENDDATA 4 22038 4 27 ENDSUBENT 4 22038 499999 ENDENTRY 4 2203899999999 ENTRY 22039 881118 22039 0 1 SUBENT 22039001 871210 22039 1 1 BIB 13 19 22039 1 2 INSTITUTE (2UK KEN) 22039 1 3 REFERENCE (J,RCA,16,104,7104) 22039 1 4 AUTHOR (O.BIRGUL,S.J.LYLE,R.WELLUM) 22039 1 5 TITLE -SOME CUMULATIVE MASS-YIELDS AND PROMPT NEUTRON 22039 1 6 YIELDS FOR SELECTED MASSES FROM 14.8 MEV NEUTRON 22039 1 7 INDUCED FISSION OF U-238. 22039 1 8 FACILITY (VDG ) 400 KV VAN DE GRAAFF ACCELERATOR, USED TO 22039 1 9 ACCELERATE DEUTERONS. 22039 1 10 INC-SOURCE (D-T ) USED TO PRODUCE 14.8 MEV NEUTRONS. 22039 1 11 SAMPLE .NO DETAILS GIVEN. 22039 1 12 METHOD (CHSEP) CHEMICAL SEPARATION AND PURIFICATION. 22039 1 13 (ACTIV) ACTIVITY MEASUREMENTS OF FISSON PRODUCTS. 22039 1 14 DETECTOR .NO DETAILS GIVEN. 22039 1 15 CORRECTION .NO DETAILS GIVEN. 22039 1 16 ERR-ANALYS (DATA-ERR) STANDARD DEVIATIONS FROM THE MEANS OF 22039 1 17 SEVERAL MEASUREMENTS. 22039 1 18 STATUS .DATA TAKEN FROM MAIN REFERENCE. 22039 1 19 HISTORY (871110C) N.O. 22039 1 20 (871210E) 22039 1 21 ENDBIB 19 22039 1 22 COMMON 1 3 22039 1 23 EN 22039 1 24 MEV 22039 1 25 1.4800E+01 22039 1 26 ENDCOMMON 1 3 22039 1 27 ENDSUBENT 1 22039 199999 SUBENT 22039002 881118 22039 2 1 BIB 5 6 22039 2 2 REACTION (92-U-238(N,F)MASS,CHN,FY) 22039 2 3 MONITOR (92-U-238(N,F)MASS,CHN,FY) 22039 2 4 MONIT-REF (,TERREL+,J,PR,92,1091,53) 22039 2 5 STATUS .DATA TAKEN FROM MAIN REFERENCE. 22039 2 6 HISTORY (871110C) N.O. 22039 2 7 (871210E) 22039 2 8 ENDBIB 6 22039 2 9 COMMON 2 3 22039 2 10 MASS-NRM MONIT 22039 2 11 NO-DIM PC/FIS 22039 2 12 99. 5.6800E+00 22039 2 13 ENDCOMMON 2 3 22039 2 14 DATA 3 9 22039 2 15 MASS DATA DATA-ERR 22039 2 16 NO-DIM PC/FIS PC/FIS 22039 2 17 9.1000E+01 3.6000E+00 2.8000E-01 22039 2 18 1.0500E+02 3.7000E+00 4.2000E-01 22039 2 19 1.0700E+02 1.7400E+00 5.0000E-02 22039 2 20 1.0900E+02 1.5600E+00 1.2000E-01 22039 2 21 1.2700E+02 1.5400E+00 2.0000E-02 22039 2 22 1.2900E+02 1.6900E+00 2.0000E-02 22039 2 23 1.3100E+02 3.6100E+00 6.0000E-02 22039 2 24 1.4300E+02 4.6400E+00 3.6000E-01 22039 2 25 1.4500E+02 3.1100E+00 1.6000E-01 22039 2 26 ENDDATA 11 22039 2 27 ENDSUBENT 3 22039 299999 ENDENTRY 2 2203999999999 ENTRY 22053 881222 22053 0 1 SUBENT 22053001 871211 22053 1 1 BIB 14 31 22053 1 2 INSTITUTE (2UK HAR) EXPERIMENTAL SITE. 22053 1 3 (1CANMCM) K.F. 22053 1 4 REFERENCE (J,NP,84,49,66) 22053 1 5 AUTHOR (J.G.CUNINGHAME,K.FRITZE,J.E.LYNN,C.B.WEBSTER) 22053 1 6 TITLE -THE RATIO OF ASYMMETRIC TO SYMMETRIC FISSION IN 22053 1 7 FISSION OF PU-239 BY NEUTRONS OF ENERGIES FROM 22053 1 8 30 KEV TO 14.7 MEV. 22053 1 9 FACILITY (VDG ) VDG AND CCW USED FOR PU IRRADIATIONS. 22053 1 10 (CCW ) 22053 1 11 (REAC ) THERMAL REACTOR USED FOR CALIBRATIONS WITH 22053 1 12 U-235. 22053 1 13 INC-SOURCE (P-T ) FOR 60 KEV NEUTRONS. 22053 1 14 (P-LI7) FOR 30, 120, 200, 300, 500 AND 1000 KEV 22053 1 15 NEUTRONS. 22053 1 16 (D-D ) FOR 6 MEV NEUTRONS. 22053 1 17 (D-T ) FOR 14.7 MEV NEUTRONS. 22053 1 18 (REAC ) THERMAL REACTOR. 22053 1 19 SAMPLE .ABOUT 5 G OF PU-239 METAL, PACKED INTO A 1 MM 22053 1 20 THICK CADMIUM CAN. IRRADIATED FOR 1 HOUR. 22053 1 21 METHOD (CHSEP) CHEMICAL SEPARATION OF FISSION PRODUCTS 22053 1 22 PRIOR TO ACTIVITY COUNTING. 22053 1 23 DETECTOR .NO INFORMATION GIVEN. 22053 1 24 MONITOR ((92-U-235(N,F)42-MO-99,CUM,FY)/ 22053 1 25 (92-U-235(N,F)47-AG-113-G,CUM,FY)) PEAK-TO-VALLEY 22053 1 26 RATIO OF THE FISSION YIELD CURVE. 22053 1 27 CORRECTION .CORRECTIONS WERE APPLIED FOR CHEMICAL YIELD, BACK- 22053 1 28 GROUND, PARALYSIS AND SELF-ABSORPTION. 22053 1 29 ERR-ANALYS (DATA-ERR ) STANDARD DEVIATIONS. 22053 1 30 STATUS .DATA TAKEN FROM MAIN REFERENCE. 22053 1 31 HISTORY (871104C) N.O. 22053 1 32 (871211E) 22053 1 33 ENDBIB 31 22053 1 34 NOCOMMON 0 0 22053 1 35 ENDSUBENT 0 22053 199999 SUBENT 22053002 881222 22053 2 1 BIB 3 5 22053 2 2 REACTION ((94-PU-239(N,F)42-MO-99,CUM,FY)/ 22053 2 3 (94-PU-239(N,F)47-AG-111-G,CUM,FY)) 22053 2 4 STATUS .DATA TAKEN FROM MAIN REFERENCE. 22053 2 5 HISTORY (871104C) N.O. 22053 2 6 (871211E) 22053 2 7 ENDBIB 5 22053 2 8 NOCOMMON 0 0 22053 2 9 DATA 5 1 22053 2 10 EN +EN-RSL -EN-RSL DATA DATA-ERR 22053 2 11 KEV KEV KEV NO-DIM NO-DIM 22053 2 12 1.4700E+04 5.0000E+02 5.0000E+02 2.5200E+00 3.0000E-01 22053 2 13 ENDDATA 3 22053 2 14 ENDSUBENT 5 22053 299999 SUBENT 22053003 881222 22053 3 1 BIB 3 5 22053 3 2 REACTION ((94-PU-239(N,F)42-MO-99,CUM,FY)/ 22053 3 3 (94-PU-239(N,F)47-AG-113-G,CUM,FY)) 22053 3 4 STATUS .DATA TAKEN FROM MAIN REFERENCE. 22053 3 5 HISTORY (871104C) N.O. 22053 3 6 (871211E) 22053 3 7 ENDBIB 5 22053 3 8 NOCOMMON 0 0 22053 3 9 DATA 5 1 22053 3 10 EN +EN-RSL -EN-RSL DATA DATA-ERR 22053 3 11 KEV KEV KEV NO-DIM NO-DIM 22053 3 12 1.4700E+04 5.0000E+02 5.0000E+02 2.9500E+00 3.5000E-01 22053 3 13 ENDDATA 3 22053 3 14 ENDSUBENT 5 22053 399999 ENDENTRY 3 2205399999999 ENTRY 22056 890207 22056 0 1 SUBENT 22056001 880804 22056 1 1 BIB 9 20 22056 1 2 INSTITUTE (2GERMNZ) EXPERIMENTAL SITE, H.O.D. 22056 1 3 (2GERJUL) S.M.Q. 22056 1 4 REFERENCE (J,JIN,33,(11),3649,7111) MAIN REFERENCE. 22056 1 5 (C,71CANT,51,7109) 22056 1 6 AUTHOR (H.O.DENSCHLAG,S.M.QAIM) 22056 1 7 TITLE -INDEPENDENT YIELDS OF I-133, I-134 AND I-135 IN 22056 1 8 THE FISSION OF TH-232 INDUCED BY REACTOR NEUTRONS 22056 1 9 AND 14.8 MEV NEUTRONS - CHARGE DISTRIBUTION IN 22056 1 10 LOW AND MEDIUM ENERGY FISSION. 22056 1 11 DETECTOR (NAICR) USED FOR GAMMA ACTIVITY MEASUREMENTS OF 22056 1 12 THE IODINE ISOTOPES. 22056 1 13 (GELI ) USED FOR GAMMA ACTIVITY MEASUREMENTS OF 22056 1 14 XE-135. 22056 1 15 PART-DET (DG ) 22056 1 16 CORRECTION .CORRECTIONS WERE APPLIED FOR CHEMICAL YIELD. 22056 1 17 STATUS .DATA TAKEN FROM MAIN REFERENCE. 22056 1 18 HISTORY (871105C) N.O. 22056 1 19 (871211E) 22056 1 20 (880804U) 22056 1 21 (880810E) 22056 1 22 ENDBIB 20 22056 1 23 NOCOMMON 0 0 22056 1 24 ENDSUBENT 0 22056 199999 SUBENT 22056003 890207 22056 3 1 BIB 10 29 22056 3 2 REACTION ((90-TH-232(N,F)ELEM/MASS,IND,FY)/ 22056 3 3 (90-TH-232(N,F)MASS,CHN,FY)) 22056 3 4 FACILITY (CCW ) COCKCROFT-WALTON ACCELERATOR. 22056 3 5 INC-SOURCE (D-T ) NEUTRON FLUX 5.0E+10 NEUTRONS/CM2 SEC. 22056 3 6 .IRRADIATION TIMES UP TO 10 SEC FOR THE AUTOMATIC 22056 3 7 SEPARATION AND 1 MIN FOR THE MANUAL SEPARATION. 22056 3 8 FOR XE-135 MEASUREMENTS THE IRRADIATION TIME WAS 22056 3 9 15 MIN. 22056 3 10 SAMPLE .ABOUT 1 G OF TH-232 IN THE FORM OF NITRATE WAS 22056 3 11 USED IN THE AUTOMATIC SEPARATION MEASUREMENTS. 22056 3 12 .ABOUT 4 G OF TH-232 IN THE FORM OF NITRATE WAS 22056 3 13 USED IN THE MANUAL SEPARATION MEASUREMENTS. 22056 3 14 METHOD (CHSEP) 22056 3 15 .FOR THE 14.8 MEV IRRADIATIONS, A SLOWER, MANUAL 22056 3 16 SEPARATION TECHNIQUE WAS USED IN ADDITION TO THE 22056 3 17 FAST METHOD MENTIONED. 22056 3 18 .THE XE-135 YIELD WAS DETERMINED BY DIRECT GAMMA- 22056 3 19 RAY SPECTROMETRY. 22056 3 20 MONITOR ((90-TH-232(N,F)ELEM/MASS,CUM,FY)/ 22056 3 21 (90-TH-232(N,F)MASS,CHN,FY)) 22056 3 22 ERR-ANALYS (DATA-ERR) THE QUOTED ERRORS INCLUDE SYSTEMATIC 22056 3 23 ERRORS AND CORRESPOND TO A CONFIDENCE LEVEL OF 22056 3 24 90 PER-CENT. 22056 3 25 FLAG (1.) UPPER LIMIT. 22056 3 26 STATUS .DATA TAKEN FROM MAIN REFERENCE. 22056 3 27 HISTORY (871105C) N.O. 22056 3 28 (871211E) 22056 3 29 (880804U) 22056 3 30 (880810E) 22056 3 31 ENDBIB 29 22056 3 32 COMMON 2 3 22056 3 33 EN EN-RSL 22056 3 34 MEV MEV 22056 3 35 1.4800E+01 3.0000E-01 22056 3 36 ENDCOMMON 2 3 22056 3 37 DATA 6 4 22056 3 38 ELEMENT MASS DATA DATA-ERR MONIT FLAG 22056 3 39 NO-DIM NO-DIM NO-DIM NO-DIM NO-DIM NO-DIM 22056 3 40 5.3000E+01 1.3300E+02 8.0000E-02 2.0000E-02 1.0000E+00 22056 3 41 5.3000E+01 1.3400E+02 1.5200E-01 5.0000E-03 1.0000E+00 22056 3 42 5.3000E+01 1.3500E+02 4.7000E-01 8.0000E-02 9.8000E-01 22056 3 43 5.4000E+01 1.3500E+02 2.0000E-02 1.0000E+0022056 3 44 ENDDATA 6 22056 3 45 ENDSUBENT 6 22056 399999 ENDENTRY 2 2205699999999 ENTRY 22062 890207 22062 0 1 SUBENT 22062001 890207 22062 1 1 BIB 13 32 22062 1 2 INSTITUTE (2UK KEN) 22062 1 3 REFERENCE (J,RCA,12,43,6907) 22062 1 4 AUTHOR (S.J.LYLE,J.SELLARS) 22062 1 5 TITLE -FINE STRUCTURE IN NUCLEAR FISSION - YIELDS FROM 22062 1 6 3 AND 14.8 MEV NEUTRON INDUCED FISSION OF U-238 22062 1 7 AND TH-232 IN THE MASS REGION 131 - 135. 22062 1 8 FACILITY (VDG ) 400 KV VAN DE GRAAFF ACCELERATOR, USED TO 22062 1 9 ACCELERATE DEUTERONS. 22062 1 10 INC-SOURCE (D-D ) USED TO PRODUCE 3 MEV NEUTRONS. FLUX WAS 22062 1 11 1.0E+08 NEUTRONS/SEC. 22062 1 12 (D-T ) USED TO PRODUCE 14.8 MEV NEUTRONS. FLUX 22062 1 13 WAS 2.0E+10 NEUTRONS/SEC. 22062 1 14 SAMPLE .HYDRATED BASIC OXIDES OR HYDROXIDES OR NITRATES. 22062 1 15 THE SAMPLES WERE COMPRESSED INTO PELLET FORM AND 22062 1 16 ENCLOSED IN SEALED CONTAINERS. 22062 1 17 METHOD (CHSEP) CHEMICAL SEPARATION AND PURIFICATION. 22062 1 18 DETECTOR (PROPC) END-WINDOW PROPORTIONAL COUNTERS WERE USED 22062 1 19 FOR ACTIVITY MEASUREMENTS FOR ZR-97, MO-99 AND THE 22062 1 20 IODINE ISOTOPES. 22062 1 21 (GEMUC) CALIBRATED GAS (GEIGER) COUNTERS WERE USED 22062 1 22 FOR THE XENON ISOTOPES. 22062 1 23 (SCIN ) THE NEUTRON FLUX WAS MONITORED WITH A PROTON- 22062 1 24 RECOIL PLASTIC SCINTILLATOR. 22062 1 25 CORRECTION .CORRECTIONS WERE APPLIED FOR CHEMICAL YIELD AND 22062 1 26 FISSION FRAGMENT DECAY DURING IRRADIATION. 22062 1 27 ERR-ANALYS (DATA-ERR) STANDARD DEVIATIONS FROM THE MEANS OF 22062 1 28 SEVERAL MEASUREMENTS. 22062 1 29 STATUS .DATA TAKEN FROM MAIN REFERENCE. 22062 1 30 HISTORY (871105C) N.O. 22062 1 31 (871211E) 22062 1 32 (880808U) IF. 22062 1 33 (880810E) 22062 1 34 ENDBIB 32 22062 1 35 NOCOMMON 0 0 22062 1 36 ENDSUBENT 0 22062 199999 SUBENT 22062002 890207 22062 2 1 BIB 4 10 22062 2 2 REACTION ((90-TH-232(N,F)MASS,CHN,FY)/ 22062 2 3 (90-TH-232(N,F)42-MO-99,CUM,FY)) 22062 2 4 FLAG (1.) NUCLIDE MEASURED ZR-97. 22062 2 5 (2.) NUCLIDE MEASURED XE-133. 22062 2 6 (3.) NUCLIDE MEASURED XE-135. 22062 2 7 STATUS .DATA TAKEN FROM MAIN REFERENCE. 22062 2 8 HISTORY (871105C) N.O. 22062 2 9 (871211E) 22062 2 10 (880808U) IF. 22062 2 11 (880810E) 22062 2 12 ENDBIB 10 22062 2 13 NOCOMMON 0 0 22062 2 14 DATA 6 3 22062 2 15 EN EN-RSL MASS DATA DATA-ERR FLAG 22062 2 16 MEV MEV NO-DIM NO-DIM NO-DIM NO-DIM 22062 2 17 1.4800E+01 3.0000E-01 9.7000E+01 1.4100E+00 8.0000E-02 1.0000E+0022062 2 18 1.4800E+01 3.0000E-01 1.3300E+02 2.3400E+00 1.2000E-01 2.0000E+0022062 2 19 1.4800E+01 3.0000E-01 1.3500E+02 2.7200E+00 9.0000E-02 3.0000E+0022062 2 20 ENDDATA 5 22062 2 21 ENDSUBENT 6 22062 299999 SUBENT 22062003 890207 22062 3 1 BIB 4 14 22062 3 2 REACTION ((92-U-238(N,F)MASS,CHN,FY)/ 22062 3 3 (92-U-238(N,F)42-MO-99,CUM,FY)) 22062 3 4 FLAG (1.) NUCLIDE MEASURED ZR-97. 22062 3 5 (2.) NUCLIDE MEASURED I-131. 22062 3 6 (3.) NUCLIDE MEASURED I-132. 22062 3 7 (4.) NUCLIDE MEASURED I-133. 22062 3 8 (5.) NUCLIDE MEASURED XE-133. 22062 3 9 (6.) NUCLIDE MEASURED I-134. 22062 3 10 (7.) NUCLIDE MEASURED XE-135. 22062 3 11 STATUS .DATA TAKEN FROM MAIN REFERENCE. 22062 3 12 HISTORY (871105C) N.O. 22062 3 13 (871211E) 22062 3 14 (880808U) IF. 22062 3 15 (880810E) 22062 3 16 ENDBIB 14 22062 3 17 NOCOMMON 0 0 22062 3 18 DATA 6 7 22062 3 19 EN EN-RSL MASS DATA DATA-ERR FLAG 22062 3 20 MEV MEV NO-DIM NO-DIM NO-DIM NO-DIM 22062 3 21 1.4800E+01 3.0000E-01 9.7000E+01 9.5000E-01 2.0000E-02 1.0000E+0022062 3 22 1.4800E+01 3.0000E-01 1.3100E+02 6.4000E-01 4.0000E-02 2.0000E+0022062 3 23 1.4800E+01 3.0000E-01 1.3200E+02 9.2000E-01 4.0000E-02 3.0000E+0022062 3 24 1.4800E+01 3.0000E-01 1.3300E+02 1.1200E+00 3.0000E-02 4.0000E+0022062 3 25 1.4800E+01 3.0000E-01 1.3300E+02 1.1900E+00 8.0000E-02 5.0000E+0022062 3 26 1.4800E+01 3.0000E-01 1.3400E+02 1.2300E+00 7.0000E-02 6.0000E+0022062 3 27 1.4800E+01 3.0000E-01 1.3500E+02 1.2600E+00 5.0000E-02 7.0000E+0022062 3 28 ENDDATA 9 22062 3 29 ENDSUBENT 6 22062 399999 SUBENT 22062004 880808 22062 4 1 BIB 5 10 22062 4 2 REACTION (90-TH-232(N,F)MASS,CHN,FY) NORMALIZED TO SELECTED 22062 4 3 CHAIN YIELDS FOR MASS 99. 22062 4 4 MONITOR (90-TH-232(N,F)42-MO-99,CHN,FY) 22062 4 5 MONIT-REF (,IYER+,J,JIN,25,465,63) 22062 4 6 (,BROOM+,J,PR/B,133,874,64) 22062 4 7 STATUS (DEP,22062002) DATA TAKEN FROM MAIN REFERENCE. 22062 4 8 HISTORY (871105C) N.O. 22062 4 9 (871211E) 22062 4 10 (880808U) IF. 22062 4 11 (880810E) 22062 4 12 ENDBIB 10 22062 4 13 NOCOMMON 0 0 22062 4 14 DATA 5 3 22062 4 15 EN EN-RSL MASS DATA MONIT 22062 4 16 MEV MEV NO-DIM PC/FIS PC/FIS 22062 4 17 1.4800E+01 3.0000E-01 9.7000E+01 2.7600E+00 1.9600E+00 22062 4 18 1.4800E+01 3.0000E-01 1.3300E+02 4.5800E+00 1.9600E+00 22062 4 19 1.4800E+01 3.0000E-01 1.3500E+02 5.3300E+00 1.9600E+00 22062 4 20 ENDDATA 5 22062 4 21 ENDSUBENT 5 22062 499999 SUBENT 22062005 880808 22062 5 1 BIB 5 11 22062 5 2 REACTION (92-U-238(N,F)MASS,CHN,FY) NORMALIZED TO SELECTED 22062 5 3 CHAIN YIELDS FOR MASS 99. 22062 5 4 MONITOR (92-U-238(N,F)42-MO-99,CHN,FY) 22062 5 5 MONIT-REF (,TERRELL+,J,PR,92,1091,53) 22062 5 6 (,IYER+,J,JIN,25,465,63) 22062 5 7 (,BROOM+,J,PR/B,133,874,64) 22062 5 8 STATUS (DEP,22062003) DATA TAKEN FROM MAIN REFERENCE. 22062 5 9 HISTORY (871105C) N.O. 22062 5 10 (871211E) 22062 5 11 (880808U) IF. 22062 5 12 (880810E) 22062 5 13 ENDBIB 11 22062 5 14 NOCOMMON 0 0 22062 5 15 DATA 5 6 22062 5 16 EN EN-RSL MASS DATA MONIT 22062 5 17 MEV MEV NO-DIM PC/FIS PC/FIS 22062 5 18 1.4800E+01 3.0000E-01 9.7000E+01 5.4000E+00 5.6800E+00 22062 5 19 1.4800E+01 3.0000E-01 1.3100E+02 3.6400E+00 5.6800E+00 22062 5 20 1.4800E+01 3.0000E-01 1.3200E+02 5.2300E+00 5.6800E+00 22062 5 21 1.4800E+01 3.0000E-01 1.3300E+02 6.5600E+00 5.6800E+00 22062 5 22 1.4800E+01 3.0000E-01 1.3400E+02 6.9900E+00 5.6800E+00 22062 5 23 1.4800E+01 3.0000E-01 1.3500E+02 7.1600E+00 5.6800E+00 22062 5 24 ENDDATA 8 22062 5 25 ENDSUBENT 5 22062 599999 ENDENTRY 5 2206299999999 ENTRY 30001 19850801 30001 0 1 SUBENT 30001001 19850801 30001 1 1 BIB 11 20 30001 1 2 INSTITUTE (3CPRAEP) 30001 1 3 REFERENCE (CHINESE J. OF NUCL. PHYS.,7,(3),235,8508) 30001 1 4 AUTHOR (LIU CONGGUI, LU HUIJUN, LI ZE, LIU YONGHUI) 30001 1 5 TITLE THE MASS DISTRIBUTION OF U-238 FISSION INDUCED BY 30001 1 6 14.9 MEV NEUTRONS 30001 1 7 FACILITY (CCW) 30001 1 8 INC-SOURCE (D-T) (2*10**9-10**10) NEUTRONS/S 30001 1 9 METHOD (GSPEC) DIRECT r-SPECTROSCOPY METHOD 30001 1 10 DETECTOR (GELI) 30001 1 11 MONITOR ABSOLUTE 30001 1 12 CORRECTION CORRECTION FOR r-SELF-ABSORPTION, GEOMETRY,r COUNT 30001 1 13 LOSSES AND SUMMING OF r-r CASCADE COINSIDENCE 30001 1 14 ERR-ANALYS UNCERTAINTIES INCLUDE: 30001 1 15 1) FISSION RATE 1.5%; 30001 1 16 2) EFFICIENCY OF GELI, DETECTOR 2.4%-4.2% 30001 1 17 3) CORRECTION FOR r-SELF-ABSORPTION 1.0% 30001 1 18 4) UNFOLD SPECTRUM 1.0% 30001 1 19 5) STATISTICAL 0.7-2.0% FOR NUCLIDES AT PEAKS 30001 1 20 AND 2.0-4.0% FOR NUCLIDES AT VALLEY 30001 1 21 6) UNCERTAINTY FROM OTHER CORRECTIONS 0.1-0.9%. 30001 1 22 ENDBIB 20 0 30001 1 23 COMMON 1 3 30001 1 24 EN 30001 1 25 MEV 30001 1 26 14.9 30001 1 27 ENDCOMMON 3 0 30001 1 28 ENDSUBENT 27 0 30001 199999 SUBENT 30001002 19850801 30001 2 1 BIB 2 2 30001 2 2 REACTION (92-U-238(N,F)ELEM/MASS,CUM,FY) 30001 2 3 SAMPLE NATURAL URANIUM 30001 2 4 ENDBIB 2 0 30001 2 5 NOCOMMON 0 0 30001 2 6 DATA 5 40 30001 2 7 ELEMENT MASS ISOMER DATA DATA-ERR 30001 2 8 NO-DIM NO-DIM NO-DIM PC/FIS PC/FIS 30001 2 9 35. 84. 1.10 0.09 30001 2 10 36. 85. 1. 1.05 0.06 30001 2 11 36. 87. 1.71 0.09 30001 2 12 36. 88. 1.94 0.10 30001 2 13 37. 89. 2.88 0.17 30001 2 14 38. 92. 4.03 0.13 30001 2 15 39. 91. 1. 4.16 0.13 30001 2 16 39. 93. 4.78 0.16 30001 2 17 39. 94. 4.55 0.31 30001 2 18 40. 95. 5.05 0.19 30001 2 19 40. 97. 5.65 0.18 30001 2 20 42. 99. 5.71 0.18 30001 2 21 43. 101. 6.00 0.36 30001 2 22 43. 104. 4.24 0.22 30001 2 23 44. 103. 4.68 0.15 30001 2 24 45. 105. 3.13 0.10 30001 2 25 45. 107. 1.61 0.12 30001 2 26 47. 111. 0.823 0.037 30001 2 27 47. 112. 1.04 0.04 30001 2 28 47. 113. 0.985 0.058 30001 2 29 48. 115. 0.834 0.039 30001 2 30 48. 117. 0.775 0.062 30001 2 31 50. 128. 1.85 0.10 30001 2 32 51. 127. 1.47 0.06 30001 2 33 51. 129. 2.03 0.07 30001 2 34 51. 130. 1.78 0.10 30001 2 35 52. 132. 4.68 0.23 30001 2 36 53. 131. 3.63 0.13 30001 2 37 53. 133. 6.00 0.19 30001 2 38 53. 134. 6.50 0.20 30001 2 39 53. 135. 5.78 0.18 30001 2 40 55. 138. 5.06 0.26 30001 2 41 56. 139. 4.62 0.36 30001 2 42 56. 140. 4.59 0.15 30001 2 43 57. 142. 3.93 0.21 30001 2 44 58. 141. 4.33 0.31 30001 2 45 58. 143. 4.20 0.14 30001 2 46 58. 146. 2.01 0.13 30001 2 47 60. 147. 2.10 0.10 30001 2 48 61. 151. 0.631 0.022 30001 2 49 ENDDATA 42 0 30001 2 50 ENDSUBENT 49 0 30001 299999 ENDENTRY 2 0 3000199999999 ENTRY 30002 19930614 30002 0 1 SUBENT 30002001 19930614 30002 1 1 BIB 11 20 30002 1 2 INSTITUTE (3CPRAEP) 30002 1 3 REFERENCE (J,RCA,64,95,9406) 30002 1 4 AUTHOR LI ZE, WANG XIUZHI, JING KEXING, CUI ANZHI, LIU DAMING,30002 1 5 LI DAMING, LIU YONGHUI, LI XUELIANG, LIU CONGGUI, 30002 1 6 SU SHUXING, TANG PEIJIA, CHIH TAHAI, ZHANG SHULAN, 30002 1 7 ZHANG SHENGDONG AND GUO JINGRU 30002 1 8 TITLE FISSION PRODUCT YIELDS FROM 11.3 MEV NEUTRON-INDUCED 30002 1 9 FISSION OF U-238 30002 1 10 FACILITY (VDGT) HI-13 TANDEM OF AEP. 30002 1 11 INC-SOURCE (D-D) ED=9.0 MEV 30002 1 12 METHOD (GSPEC,CHSEP) 30002 1 13 DETECTOR (GELI,HPGE) GELI, HPGE R DETECT OR AND B-DETECTOR 30002 1 14 MONITOR ABSOLUTE MEASUREMENT 30002 1 15 CORRECTION CORRECTED FOR THE SELF-ABSORPTION OF THE r-RAYS,THE 30002 1 16 CASCADE COINCIDENCE LOSSES,THE PILE-UP LOSSES IN THE 30002 1 17 COUNTING SYSTEM, AND THE INFLUENCE OF THE BACKGROUND 30002 1 18 NEUTRONS. 30002 1 19 ERR-ANALYS UNCERTAINTIES(1SIGMA) WERE OBTAINED BY CONSIDERING OF 30002 1 20 ALL KNOWN SOURCES OF RANDOM ERRORS WITH THE USUAL LOW 30002 1 21 OF ERROR PROPAGATION. 30002 1 22 ENDBIB 20 0 30002 1 23 COMMON 1 3 30002 1 24 EN 30002 1 25 MEV 30002 1 26 11.3 30002 1 27 ENDCOMMON 3 0 30002 1 28 ENDSUBENT 27 0 30002 199999 SUBENT 30002002 19930614 30002 2 1 BIB 4 4 30002 2 2 REACTION (92-U-238(N,F)ELEM/MASS,CUM,FY) 30002 2 3 SAMPLE NATURAL URANIUM,DISKS 16MM IN DIAMETER, ABOUT 2G. 30002 2 4 METHOD (GSPEC) 30002 2 5 DETECTOR (GELI,HPGE) 30002 2 6 ENDBIB 4 0 30002 2 7 NOCOMMON 0 0 30002 2 8 DATA 4 31 30002 2 9 ELEMENT MASS DATA DATA-ERR 30002 2 10 NO-DIM NO-DIM PC/FIS PC/FIS 30002 2 11 36. 87. 1.77 0.13 30002 2 12 37. 88. 2.48 0.13 30002 2 13 37. 89. 2.83 0.12 30002 2 14 38. 91. 3.93 0.15 30002 2 15 38. 92. 4.18 0.14 30002 2 16 39. 94. 4.48 0.16 30002 2 17 40. 95. 5.22 0.18 30002 2 18 41. 97. 5.28 0.20 30002 2 19 42. 99. 5.74 0.24 30002 2 20 43. 101. 5.61 0.24 30002 2 21 43. 104. 3.78 0.15 30002 2 22 44. 103. 5.20 0.20 30002 2 23 44. 105. 3.64 0.18 30002 2 24 45. 107. 2.06 0.11 30002 2 25 47. 112. 0.53 0.03 30002 2 26 50. 128. 0.927 0.074 30002 2 27 51. 127. 0.87 0.06 30002 2 28 51. 129. 1.50 0.09 30002 2 29 52. 132. 5.36 0.21 30002 2 30 53. 131. 3.23 0.14 30002 2 31 53. 133. 6.66 0.25 30002 2 32 53. 134. 6.28 0.27 30002 2 33 54. 135. 5.91 0.24 30002 2 34 55. 138. 5.85 0.29 30002 2 35 56. 139. 5.10 0.30 30002 2 36 56. 140. 5.00 0.19 30002 2 37 56. 141. 4.96 0.34 30002 2 38 58. 143. 4.28 0.16 30002 2 39 59. 146. 2.59 0.13 30002 2 40 60. 147. 2.39 0.10 30002 2 41 60. 149. 1.9 0.10 30002 2 42 ENDDATA 33 0 30002 2 43 ENDSUBENT 42 0 30002 299999 SUBENT 30002003 19930614 30002 3 1 BIB 4 4 30002 3 2 REACTION (92-U-238(N,F)ELEM/MASS,CUM,FY) 30002 3 3 SAMPLE NATURAL URANIUM,DISKS 16MM IN DIAMETER, ABOUT 2G. 30002 3 4 METHOD (RCHEM) 30002 3 5 DETECTOR (GELI) A AND B COUNTER 30002 3 6 ENDBIB 4 0 30002 3 7 NOCOMMON 0 0 30002 3 8 DATA 4 14 30002 3 9 ELEMENT MASS DATA DATA-ERR 30002 3 10 NO-DIM NO-DIM PC/FIS PC/FIS 30002 3 11 42. 99. 5.80 0.17 30002 3 12 46. 109. 1.10 0.09 30002 3 13 47. 111. 0.57 0.06 30002 3 14 47. 113. 0.49 0.03 30002 3 15 48. 115. 0.43 0.05 30002 3 16 50. 121. 0.35 0.10 30002 3 17 51. 127. 0.94 0.04 30002 3 18 56. 140. 5.72 0.23 30002 3 19 56. 141. 4.81 0.14 30002 3 20 58. 144. 4.20 0.20 30002 3 21 60. 147. 2.53 0.08 30002 3 22 62. 153. 0.415 0.025 30002 3 23 63. 156. 0.0954 0.0054 30002 3 24 65. 161. 0.0094 0.0009 30002 3 25 ENDDATA 16 0 30002 3 26 ENDSUBENT 25 0 30002 399999 ENDENTRY 3 0 3000299999999 ENTRY 30003 20010910 30003000 1 SUBENT 30003001 20010910 30003001 1 BIB 12 17 30003001 2 INSTITUTE (3CPRAEP) 30003001 3 REFERENCE (COMMUN. OF NUCL. DATA PROGRESS,25,4,0109) 30003001 4 AUTHOR (FENG JIN, LIU YONGHUI, YANG YI ETC.) 30003001 5 TITLE FISSION PRODUCT YIELDS FROM 22 MEV NEUTRON-INDUCED 30003001 6 FISSION OF 235-U 30003001 7 FACILITY (DVGT)HI-13 AT CIAE 30003001 8 INC-SOURCE (D-T) 30003001 9 METHOD (GSPEC) DIRECT r-SPECTROSCOPY METHOD 30003001 10 DETECTOR (GELI) 30003001 11 MONITOR ABSOLUTE 30003001 12 SAMPLE METAL URANIUM DISK, DIEMETER 16mm, WITH ISOTOPE COM- 30003001 13 POSITION OF 1.1% 234-U, 90.2% 235-U, 0.3% 236-U, 30003001 14 8.4% 238-U. 30003001 15 CORRECTION CORRECTION FOR r-SELF-ABSORPTION, CASCADE COINSIDENCE 30003001 16 LOSSES, FLUENCE OF BACKGROUND NEUTRON, FISSION FROM 30003001 17 238-U, INDEPEMDENCE YIELD NOT INCLUDED 30003001 18 ERR-ANALYS TOTAL ERROR 30003001 19 ENDBIB 17 0 30003001 20 COMMON 1 3 30003001 21 EN 30003001 22 MEV 30003001 23 22.0 30003001 24 ENDCOMMON 3 0 30003001 25 ENDSUBENT 24 0 3000300199999 SUBENT 30003002 20010910 30003002 1 BIB 1 1 30003002 2 REACTION (92-U-235(N,F)ELEM/MASS,CHN,FY) 30003002 3 ENDBIB 2 0 30003002 4 NOCOMMON 0 0 30003002 5 DATA 3 28 30003002 6 MASS DATA DATA-ERR 30003002 7 NO-DIM NO-DIM NO-DIM 30003002 8 85 0.99 0.08 30003002 9 87 2.61 0.11 30003002 10 88 3.26 0.15 30003002 11 89 4.22 0.25 30003002 12 91 4.25 0.16 30003002 13 92 4.93 0.24 30003002 14 94 4.85 0.22 30003002 15 95 4.67 0.18 30003002 16 97 5.08 0.19 30003002 17 99 4.90 0.18 30003002 18 101 4.14 0.17 30003002 19 104 3.10 0.18 30003002 20 105 2.47 0.15 30003002 21 112 1.51 0.15 30003002 22 115 1.20 0.14 30003002 23 127 1.49 0.13 30003002 24 128 2.06 1.45 30003002 25 129 2.37 0.50 30003002 26 131 3.70 0.83 30003002 27 132 4.16 0.15 30003002 28 133 5.66 0.25 30003002 29 135 5.84 0.29 30003002 30 138 5.85 0.59 30003002 31 140 4.45 0.17 30003002 32 142 3.76 0.18 30003002 33 143 4.25 0.18 30003002 34 147 2.10 0.12 30003002 35 151 0.45 0.02 30003002 36 ENDDATA 30 0 30003002 37 ENDSUBENT 36 0 3000300299999 ENDENTRY 2 0 3000399999999 ENTRY 30004 20010910 30004000 1 SUBENT 30004001 20010910 30004001 1 BIB 12 16 30004001 2 INSTITUTE (3CPRAEP) 30004001 3 REFERENCE (COMMUN. OF NUCL. DATA PROGRESS,25,10,0109) 30004001 4 AUTHOR (YANG YI, LIU YONGHUI, BAO JIE ETC.) 30004001 5 TITLE FISSION PRODUCT YIELDS FROM 19.1 MEV NEUTRON-INDUCED 30004001 6 FISSION OF 238-U 30004001 7 FACILITY (DVGT)5SDH-2.2X1.7 MV AT CIAE 30004001 8 INC-SOURCE (D-T) 30004001 9 METHOD (GSPEC) DIRECT r-SPECTROSCOPY METHOD 30004001 10 DETECTOR (GELI) 30004001 11 MONITOR ABSOLUTE 30004001 12 SAMPLE METAL NATURAL URANIUM DISK, DIEMETER 16mm, ABOUT 2g, 30004001 13 SEALED IN A PURE ALUMINIUM FOIL OF 0.2 mm THICKNESS 30004001 14 CORRECTION CORRECTION FOR r-SELF-ABSORPTION, CASCADE COINSIDENCE 30004001 15 LOSSES, FLUENCE OF BACKGROUND NEUTRON, FISSION FROM 30004001 16 235-U, INDEPEMDENCE YIELD NOT INCLUDED 30004001 17 ERR-ANALYS TOTAL ERROR 30004001 18 ENDBIB 16 0 30004001 19 COMMON 1 3 30004001 20 EN 30004001 21 MEV 30004001 22 19.1 30004001 23 ENDCOMMON 3 0 30004001 24 ENDSUBENT 23 0 3000400199999 SUBENT 30004002 20010910 30004002 1 BIB 1 1 30004002 2 REACTION (92-U-238(N,F)ELEM/MASS,CHN,FY) 30004002 3 ENDBIB 2 0 30004002 4 NOCOMMON 0 0 30004002 5 DATA 3 36 30004002 6 MASS DATA DATA-ERR 30004002 7 NO-DIM NO-DIM NO-DIM 30004002 8 85 1.130 0.099 30004002 9 87 1.871 0.070 30004002 10 88 2.370 0.107 30004002 11 89 3.024 0.173 30004002 12 91 3.392 0.105 30004002 13 92 3.815 0.165 30004002 14 93 4.159 0.251 30004002 15 94 3.730 0.170 30004002 16 95 4.564 0.139 30004002 17 97 5.498 0.165 30004002 18 99 5.824 0.206 30004002 19 101 4.822 0.211 30004002 20 103 4.110 0.138 30004002 21 104 3.823 0.175 30004002 22 105 3.011 0.097 30004002 23 112 1.570 0.065 30004002 24 115 1.277 0.075 30004002 25 127 1.818 0.073 30004002 26 128 1.987 0.161 30004002 27 129 2.066 0.086 30004002 28 130 3.000 0.985 30004002 29 131 3.969 0.141 30004002 30 132 4.529 0.157 30004002 31 133 5.704 0.181 30004002 32 134 5.762 0.302 30004002 33 135 5.503 0.326 30004002 34 138 5.046 0.448 30004002 35 140 4.178 0.136 30004002 36 141 4.632 0.301 30004002 37 142 3.663 0.145 30004002 38 143 3.595 0.162 30004002 39 146 2.212 0.121 30004002 40 147 1.859 0.063 30004002 41 149 1.296 0.089 30004002 42 151 0.686 0.033 30004002 43 156 0.169 0.072 30004002 44 ENDDATA 38 0 30004002 45 ENDSUBENT 44 0 3000400299999 ENDENTRY 2 0 3000499999999 ENTRY 30005 20010910 30005000 1 SUBENT 30005001 20010910 30005001 1 BIB 12 14 30005001 2 INSTITUTE (3CPRAEP) 30005001 3 REFERENCE (COMMUN. OF NUCL. DATA PROGRESS,26,2,0112) 30005001 4 AUTHOR (LIU YONGHUI, YANG YI, FENG JIN ETC.) 30005001 5 TITLE THE MASS DISTRIBUTIONS IN 22 MEV NEUTRON-INDUCED 30005001 6 FISSION OF 238-U 30005001 7 FACILITY (DVGT)HI-13 AT CIAE 30005001 8 INC-SOURCE (D-T) 30005001 9 METHOD (GSPEC) DIRECT r-SPECTROSCOPY METHOD 30005001 10 DETECTOR (GELI) 30005001 11 MONITOR ABSOLUTE 30005001 12 SAMPLE NATURAL URANIUM METAL DISK, DIEMETER 16mm, ABOUT 1.5g 30005001 13 CORRECTION CORRECTION FOR r-SELF-ABSORPTION, CASCADE COINSIDENCE 30005001 14 LOSSES, FLUENCE OF BACKGROUND NEUTRON 30005001 15 ERR-ANALYS TOTAL ERROR 30005001 16 ENDBIB 14 0 30005001 17 COMMON 1 3 30005001 18 EN 30005001 19 MEV 30005001 20 22.0 30005001 21 ENDCOMMON 3 0 30005001 22 ENDSUBENT 21 0 3000500199999 SUBENT 30005002 20010910 30005002 1 BIB 1 1 30005002 2 REACTION (92-U-238(N,F)ELEM/MASS,CHN,FY) 30005002 3 ENDBIB 1 0 30005002 4 NOCOMMON 0 0 30005002 5 DATA 3 33 30005002 6 MASS DATA DATA-ERR 30005002 7 NO-DIM NO-DIM NO-DIM 30005002 8 84 0.808 0.108 30005002 9 85 1.666 0.096 30005002 10 87 1.898 0.041 30005002 11 88 2.641 0.052 30005002 12 89 3.682 0.107 30005002 13 91 3.584 0.019 30005002 14 92 3.939 0.017 30005002 15 93 4.518 0.237 30005002 16 94 3.998 0.058 30005002 17 95 5.808 0.089 30005002 18 97 6.09 0.180 30005002 19 99 5.991 0.103 30005002 20 101 5.031 0.083 30005002 21 103 4.017 0.024 30005002 22 104 4.127 0.093 30005002 23 105 3.318 0.025 30005002 24 112 1.626 0.016 30005002 25 115 1.405 0.040 30005002 26 127 1.836 0.024 30005002 27 128 2.061 0.865 30005002 28 131 3.906 0.073 30005002 29 132 4.313 0.053 30005002 30 133 5.696 0.021 30005002 31 134 6.035 0.178 30005002 32 135 6.032 0.232 30005002 33 138 4.758 0.126 30005002 34 140 4.054 0.044 30005002 35 141 3.806 0.213 30005002 36 142 3.517 0.070 30005002 37 143 3.706 0.019 30005002 38 146 2.175 0.129 30005002 39 147 1.754 0.140 30005002 40 151 0.445 0.017 30005002 41 ENDDATA 35 0 30005002 42 ENDSUBENT 41 0 3000500299999 ENDENTRY 2 0 3000599999999 ENTRY 30006 20010910 30006000 1 SUBENT 30006001 20010910 30006001 1 BIB 12 17 30006001 2 INSTITUTE (3CPRAEP) 30006001 3 REFERENCE (COMMUN. OF NUCL. DATA PROGRESS,26,8,0112) 30006001 4 AUTHOR (BAO JIE, YANG YI, LIU YONGHUI ETC.) 30006001 5 TITLE FISSION PRODUCT YIELDS FROM 19.1 MEV NEUTRON-INDUCED 30006001 6 FISSION OF 235-U 30006001 7 FACILITY (DVGT)5SDH-2.2X1.7 MV AT CIAE 30006001 8 INC-SOURCE (D-T) 30006001 9 METHOD (GSPEC) DIRECT r-SPECTROSCOPY METHOD 30006001 10 DETECTOR (GELI) 30006001 11 MONITOR ABSOLUTE 30006001 12 SAMPLE METAL URANIUM DISK, DIEMETER 16mm, WITH ISOTOPE COMPO- 30006001 13 SITION OF 1.1% 234-U, 90.2% 235-U, 0.3% 236-U, 30006001 14 8.4% 238-U. 30006001 15 CORRECTION CORRECTION FOR r-SELF-ABSORPTION, CASCADE COINSIDENCE 30006001 16 LOSSES, FLUENCE OF BACKGROUND NEUTRON, FISSION FROM 30006001 17 235-U, INDEPEMDENCE YIELD NOT MEASURED 30006001 18 ERR-ANALYS TOTAL ERROR 30006001 19 ENDBIB 17 0 30006001 20 COMMON 1 3 30006001 21 EN 30006001 22 MEV 30006001 23 19.1 30006001 24 ENDCOMMON 3 0 30006001 25 ENDSUBENT 24 0 3000600199999 SUBENT 30006002 20010910 30006002 1 BIB 1 1 30006002 2 REACTION (92-U-235(N,F)ELEM/MASS,CHN,FY) 30006002 3 ENDBIB 1 0 30006002 4 NOCOMMON 0 0 30006002 5 DATA 3 35 30006002 6 MASS DATA DATA-ERR 30006002 7 NO-DIM NO-DIM PER-CENT 30006002 8 84 0.605 16.10 30006002 9 85 1.489 6.60 30006002 10 87 2.76 4.0 30006002 11 88 3.208 4.10 30006002 12 89 3.902 5.40 30006002 13 91 3.874 3.90 30006002 14 92 4.485 9.10 30006002 15 93 4.22 7.0 30006002 16 94 4.194 4.90 30006002 17 95 4.537 3.80 30006002 18 97 4.773 3.30 30006002 19 99 5.6 3.30 30006002 20 101 3.83 4.30 30006002 21 103 3.062 3.10 30006002 22 104 3.327 5.70 30006002 23 105 2.922 6.0 30006002 24 112 2.314 11.0 30006002 25 115 2.022 6.0 30006002 26 117 1.646 10.90 30006002 27 127 2.287 7.30 30006002 28 128 2.551 64.10 30006002 29 129 2.786 9.10 30006002 30 131 4.043 54.20 30006002 31 132 3.82 3.40 30006002 32 133 5.209 3.30 30006002 33 134 6.245 46.70 30006002 34 135 5.44 4.40 30006002 35 138 4.376 12.20 30006002 36 140 3.929 4.10 30006002 37 142 2.97 5.10 30006002 38 143 3.172 5.20 30006002 39 146 1.544 11.50 30006002 40 147 1.706 7.20 30006002 41 149 0.85 46.90 30006002 42 151 0.636 5.40 30006002 43 ENDDATA 37 0 30006002 44 ENDSUBENT 43 0 3000600299999 ENDENTRY 2 0 3000699999999 ENTRY 30267 850308 30267 0 1 SUBENT 30267001 840511 30267 1 1 BIB 14 41 30267 1 2 INSTITUTE (3HUNKOS) 30267 1 3 REFERENCE (C,73KIEV,3,323,7305)SUPERSEDED BY CSIKAI'S PRIV.COMM. 30267 1 4 (P,INDC(HUN)-11,26,7309)BRIEF,NO DATA 30267 1 5 AUTHOR (S.DAROCZY,E.GERMAN,P.RAICS,S.NAGY,J.CSIKAI) 30267 1 6 TITLE SOME U-238 FISSION YIELDS FOR 14.4 MEV NEUTRONS 30267 1 7 SAMPLE 930 MG/CM**2 THICK AND 19 MM IN DIAMETER NATURAL U3-08 30267 1 8 SAMPLE, IRRADIATED BETWEEN TWO AL FOILS 0.1 MM THICK 30267 1 9 AND COVERED WITH CADMIUM 30267 1 10 METHOD DIRECT GAMMA SPECTROMETRY OF THE SAMPLE WITHOUT CHEMI- 30267 1 11 CAL SEPARATION OR APPLYING THE RECOIL EFFECT. 30267 1 12 DETECTOR (GELI) 28 CM**3 GE(LI) DETECTOR WITH FOLLOWING SPECIFI-30267 1 13 CATIONS = 30267 1 14 .RESOLUTION = 7 KEV FWHM AT 661.6 KEV 30267 1 15 .EFFICIENCY = EXPERIMENTALLY DETERMINED IN THE 30267 1 16 60-2450 KEV REGION 30267 1 17 PART-DET (DG) DECAY GAMMAS 30267 1 18 ANALYSIS DETERMINATION OF THE GAMMA INTENSITIES AS WELL AS THE 30267 1 19 ANALYSIS OF DECAY CURVES WERE PERFORMED USING COMPUTER 30267 1 20 LEAST SQUARES FITTING METHOD 30267 1 21 MONITOR THE NUMBER OF FISSIONS WAS CALCULATED FROM = 30267 1 22 1(13-AL-27(N,A)11-NA-24,,SIG) 30267 1 23 USED FOR DETERMINING THE NEUTRON FLUX, 30267 1 24 2(92-U-238(N,F),,SIG) 30267 1 25 . ACCEPTED VALUES SEE BELOW. 30267 1 26 CORRECTION SELF-ABSORPTION CORRECTION FOR LOW ENERGY GAMMA RAYS 30267 1 27 WAS ESTIMATED USING URANIUM SAMPLES OF VARIOUS THICK- 30267 1 28 NESSES 30267 1 29 ERR-ANALYS (DATA-ERR) THE DATA ERROR INCLUDES = 30267 1 30 .THE STATISTICAL ERROR 30267 1 31 .THE UNCERTAINTY ON THE DETECTOR'S EFFICIENCY = 5 PER-30267 1 32 CENT 30267 1 33 THE UNCERTAINTY ON THE NUMBER OF FISSION (7 PER-CENT) 30267 1 34 AND ON THE GAMMA INTENSITIES IS NOT INCLUDED IN THE 30267 1 35 DATA ERROR 30267 1 36 STATUS DATA FROM CSIKAI'S PRIV.COMM. (4 DEC 1973) 30267 1 37 (APRVD) APPROVED BY CSIKAI AT SMOLENICE (4 SEP 74) 30267 1 38 (SPSDD,30639001) SUPERSEDED BY EXFOR 30639 CONTAINING 30267 1 39 REVISED AND NEW DATA FROM AK 18,317 30267 1 40 HISTORY (741022C) CA. 30267 1 41 (800729U) ML. ISOMER FLAG ADDED TO DATA TABLES 30267 1 42 (821105A) ML.DATA SUPERSEDED 30267 1 43 ENDBIB 41 30267 1 44 COMMON 6 3 30267 1 45 EN EN-RSL MONIT 1MONIT-ERR 1MONIT 2MONIT-ERR 230267 1 46 MEV MEV MB MB MB MB 30267 1 47 1.4400E+01 2.0000E-01 1.1700E+02 2.0000E+00 1.1650E+03 2.2000E+0130267 1 48 ENDCOMMON 6 3 30267 1 49 ENDSUBENT 6 30267 199999 SUBENT 30267002 850308 30267 2 1 BIB 4 53 30267 2 2 REACTION (92-U-238(N,F),CUM,FY) 30267 2 3 EXPERIMENTAL RESULTS 30267 2 4 DECAY-DATA ((1.)36-KR-85-M,4.4HR,DG,151.1,.76) 30267 2 5 ((2.)36-KR-87,76.MIN,DG,403.0,.806) 30267 2 6 ((3.)38-SR-91,50.MIN,DG,555.6,.58) 30267 2 7 ((4.)38-SR-92,2.71HR,DG,1386.0,.90) 30267 2 8 ((5.)38-SR-91,9.7HR,DG,653.0,.12) 30267 2 9 ((6.)38-SR-91,9.7HR,DG,749.8,.24) 30267 2 10 ((7.)38-SR-91,9.7HR,DG,1024.3,.33) 30267 2 11 ((8.)40-ZR-95,65.5D,DG,724.2,.43) 30267 2 12 ((9.)40-ZR-95,65.5D,DG,756.7,.546) 30267 2 13 ((10.)40-ZR-95,35.D,DG,765.8,.99) 30267 2 14 ((11.)41-NB-97-G,74.MIN,DG,658.2,0.99) 30267 2 15 ((12.)40-ZR-97,16.8HR,DG,743.4,.94) 30267 2 16 ((13.)43-TC-99-G,6.0HR,DG,140.4,0.810) 30267 2 17 ((14.)42-MO-99,66.7HR,DG,739.3,.120) 30267 2 18 ((15.)44-RU-103,39.5D,DG,497.1,.900) 30267 2 19 ((16.)45-RH-105-G,35.5HR,DG,319.2,0.196) 30267 2 20 ((17.)44-RU-105,4.4HR,DG,724.2,.445) 30267 2 21 ((18.)46-PD-112,3.2HR,DG,617.4,.435) 30267 2 22 ((19.)51-SB-127,3.8D,DG,684.9,.368) 30267 2 23 ((20.)52-TE-132,78.HR,DG,228.2,.880) 30267 2 24 ((21.)53-I-132-G,2.4HR,DG,522.6,0.156) 30267 2 25 ((22.)53-I-132-G,2.4HR,DG,630.2,0.135) 30267 2 26 ((23.)53-I-132-G,2.4HR,DG,667.7,0.98) 30267 2 27 ((24.)53-I-132-G,2.4HR,DG,772.7,0.750) 30267 2 28 ((25.)53-I-132-G,2.4HR,DG,954.6,0.167) 30267 2 29 ((26.)53-I-131,8.05D,DG,364.5,.790) 30267 2 30 ((27.)53-I-133-G,20.8HR,DG,529.9,0.89) 30267 2 31 ((28.)53-I-134-G,52.0MIN,DG,847.0,0.96) 30267 2 32 ((29.)53-I-134-G,52.0MIN,DG,884.0,0.66) 30267 2 33 ((30.)54-XE-135-G,9.15HR,DG,249.7,0.920) 30267 2 34 ((31.)53-I-135,6.7HR,DG,1260.5,.349) 30267 2 35 ((32.)56-BA-140,12.8D,DG,537.3,.240) 30267 2 36 ((33.)57-LA-140,40.2HR,DG,487.0,.465) 30267 2 37 ((34.)57-LA-140,40.2HR,DG,815.8,.240) 30267 2 38 ((35.)57-LA-140,40.2HR,DG,1596.2,.965) 30267 2 39 ((36.)58-CE-141,32.5D,DG,145.4,.493) 30267 2 40 ((37.)58-CE-143,33.4HR,DG,293.2,.413) 30267 2 41 ((38.)60-ND-147,11.1D,DG,531.0,.131) 30267 2 42 COMMENT THE YIELDS PRESENTED IN THE TABLE BELOW ARE THE DIRECT 30267 2 43 EXPERIMENTAL RESULTS BEFORE AVERAGING. THUS, FOR A 30267 2 44 NUMBER OF NUCLIDES, ARE GIVEN THE YIELDS OBTAINED FROM 30267 2 45 DIFFERENT GAMMA LINES OR FOR VARIOUS GAMMA INTENSITIES.30267 2 46 AVERAGED-RECOMMENDED- VALUES ARE GIVEN IN SUBENTRY 2. 30267 2 47 FLAG (2.) THE GAMMA TRANSITION MEASURED BELONGS TO THE 30267 2 48 GRAND-DAUGHTER OF THE FISSION PRODUCT 30267 2 49 (3.) THE YIELD WAS CALCULATED USING 2 DIFFERENT VALUES 30267 2 50 FOR THE INTENSITY OF THE MEASURED GAMMA TRANSITION 30267 2 51 (4.) THE YIELD WAS CALCULATED USING 2 DIFFERENT VALUES 30267 2 52 FOR THE INTENSITY OF THE MEASURED GAMMA TRANSITION 30267 2 53 WHICH HERE BELONGS TO THE GRAND-DAUGHTER OF THE FISSION30267 2 54 PRODUCT 30267 2 55 ENDBIB 53 30267 2 56 NOCOMMON 0 0 30267 2 57 NODATA 0 0 30267 2 58 ENDSUBENT 0 30267 299999 SUBENT 30267003 840511 30267 3 1 BIB 3 9 30267 3 2 REACTION (92-U-238(N,F),CUM,FY) 30267 3 3 RECOMMENDED CUMULATIVE YIELD 30267 3 4 FLAG (2.) THIS VALUE IS THE WEIGHTED AVERAGE OF THE YIELDS 30267 3 5 MEASURED FROM DIFFERENT GAMMA LINES-FOR THE NUCLIDE IN 30267 3 6 QUESTION- WHICH ARE GIVEN IN SUBENTRY 2. 30267 3 7 STATUS (DEP) DATA FLAGGED BY 2. ARE THE WEIGHTED AVERAGE OF 30267 3 8 THE CORRESPONDING YIELDS IN SUBENTRY 2 FOR THE NUCLIDE 30267 3 9 IN QUESTION. THE OTHER DATA ARE IDENTICAL TO THE ONES 30267 3 10 OF SUBENTRY 2. 30267 3 11 ENDBIB 9 30267 3 12 NOCOMMON 0 0 30267 3 13 NODATA 0 0 30267 3 14 ENDSUBENT 0 30267 399999 ENDENTRY 3 3026799999999 ENTRY 30639 850411 30639 0 1 SUBENT 30639001 850411 30639 1 1 BIB 11 34 30639 1 2 INSTITUTE (3HUNKOS) 30639 1 3 REFERENCE (J,AK,18,317,76) FINAL DETAILED RESULTS 30639 1 4 (P,INDC(SEC)-61,53,7710) BRIEF,GRAPH ONLY 30639 1 5 AUTHOR (S.DAROCZY,P.RAICS,S.NAGY,L.KOEVER,I.HAMVAS,E.GERMAN) 30639 1 6 TITLE EXPERIMENTAL RESULTS OF MASS DISTRIBUTION OF U-238 30639 1 7 FISSION INDUCED BY 14 MEV NEUTRONS 30639 1 8 FACILITY NO INFORMATION 30639 1 9 SAMPLE NATURAL URANIUM,U308.DETAILS FOR INDIVIDUAL SAMPLES OF 30639 1 10 THE 3 EXPERIMENTS ARE GIVEN IN SUBENTRIES 2,3,4,7,8. 30639 1 11 METHOD DIRECT GAMMA-SPECTOMETRY OF FISSION PRODUCTS 30639 1 12 CORRECTION GAMMA SPECTRA WERE CORRECTED FOR RANDOM PULSE PILE-UP 30639 1 13 AND COINCIDENCES. 30639 1 14 CORRECTIONS FOR GAMMA RAY ATTENUATION WERE DETERMINED 30639 1 15 EXPERIMENTALLY USING URANIUM AND THORIUM SAMPLES OF 30639 1 16 DIFFERENT THICKNESSES. 30639 1 17 COMMENT THE WORK CONSISTS OF 3 DIFFERENT EXPERIMENTS. RESULTS 30639 1 18 ARE GIVEN FOR EACH EXPERIMENT AS WELL AS WEIGHTED 30639 1 19 AVERAGES AND DEDUCED CHAIN AND FRACTIONAL YIELDS. 30639 1 20 SUBENT 02-EXPERIMENT 1 (1969),CUMULATIVE YIELDS 30639 1 21 SUBENT 03-EXPERIMENT 2 (1971),CUMULATIVE YIELDS 30639 1 22 SUBENT 04-EXPERIMENT 3 (1973),CUMULATIVE YIELDS 30639 1 23 SUBENT 05-WEIGHTED AVERAGE OF CUMULATIVE YIELDS 30639 1 24 SUBENT 06-CHAIN YIELDS 30639 1 25 SUBENT 07-EXPERIMENT 1 (1969),INDEPENDENT YIELDS 30639 1 26 SUBENT 08-EXPERIMENT 2 (1971),INDEPENDENT YIELDS 30639 1 27 SUBENT 09-WEIGHTED AVERAGE OF INDEPENDENT YIELDS 30639 1 28 SUBENT 10-FRACTIONAL INDEPENDENT YIELDS 30639 1 29 STATUS DATA COMPILED FROM TABLES II AND III OF FIRST REFERENCE30639 1 30 HISTORY (821105C) ML. 30639 1 31 (841212U) ML.DECAY DATA MOVED TO RESPECTIVE SUBENTRIES 30639 1 32 DECAY FLAGS CHANGED AND DATA SECTION 30639 1 33 REARRANGED AVOIDING REPETION OF COLUMN 30639 1 34 HEADINGS, SUBENTRIES 2,3,4,7,8. 30639 1 35 EN-ERR CORRECTED IN SUBENTRY 3. 30639 1 36 ENDBIB 34 30639 1 37 NOCOMMON 0 0 30639 1 38 ENDSUBENT 0 30639 199999 SUBENT 30639002 841217 30639 2 1 BIB 13 88 30639 2 2 EXP-YEAR (69) FIRST EXPERIMENT 30639 2 3 REACTION (92-U-238(N,F)ELEM/MASS,CUM,FY) LONG LIVED PRODUCTS 30639 2 4 INC-SOURCE NEUTRON FLUX=(7.80+-0.36)*10**6 N/(S*CM**2) RANDOM 30639 2 5 ERROR,OR +-3 PERCENT SYSTEMATIC ERROR 30639 2 6 IRRADIATION TIME=29.25 HOURS 30639 2 7 NUMBER OF FISSION EVENTS = 5.41*10**9 30639 2 8 SAMPLE 2640 GRAMS,THICKNESS=1.47 MM OR 921.4 MG/CM**2, 30639 2 9 DIAMETER=19.1 MM. 30639 2 10 DETECTOR (GELI).27 CCM, 4000 CHANNEL PULSE HEIGHT ANALYSER, 30639 2 11 RESOLUTION AT 662 KEV = 7.3 KEV. 30639 2 12 ANALYSIS 47 GAMMA SPECTRA WERE RECORDED AND ANALYSED BY THE 30639 2 13 COMPUTER PROGRAM SIRIUS,BASED ON A LEAST SQUARES 30639 2 14 FITTING PROCEDURE.COMPLETE DECAY CURVES FROM 1.4 HRS. 30639 2 15 TO 149 DAYS AFTER IRRADIATION WERE ANALYSED. 30639 2 16 MONITOR (13-AL-27(N,A)11-NA-24,,SIG) MEASURED WITH GE(LI) DET. 30639 2 17 MONIT-REF (,H.VONACH+,J,ZP,273,155,70) 30639 2 18 DECAY-DATA PARENT DAUGHTER RELATIONSHIPS INDICATED BY FLAGS 30639 2 19 ((1.)38-SR-91,9.48HR,DG,653.0,0.111) 30639 2 20 ((2.)38-SR-91,9.48HR,DG,749.8,0.231) 30639 2 21 ((3.)38-SR-91,9.48HR,DG,1024.3,0.334) 30639 2 22 ((4.)38-SR-91,9.48HR) 30639 2 23 ((4.)39-Y-91-M,49.7MIN,DG,555.6,0.558) 30639 2 24 ((5.)38-SR-92,2.71HR,DG,1383.9,0.9) 30639 2 25 ((6.)40-ZR-95,62.5D) 30639 2 26 ((6.)41-NB-95-G,35.1D,DG,765.8,0.998) 30639 2 27 ((7.)40-ZR-97,16.8HR) 30639 2 28 ((7.)41-NB-97-G,73.6MIN,DG,658.2,0.981) 30639 2 29 ((8.)40-ZR-97,16.8HR) 30639 2 30 ((8.)41-NB-97-M,54.SEC,DG,743.4,0.933) 30639 2 31 ((9.)42-MO-99,66.02HR,DG,739.6,0.120) 30639 2 32 ((10.)42-MO-99,66.02HR) 30639 2 33 ((10.)43-TC-99-M,6.02HR,DG,140.4,0.810) 30639 2 34 ((11.)44-RU-103,39.6D,DG,497.1,0.89) 30639 2 35 ((12.)44-RU-105,4.44HR,DG,724.2,0.49) 30639 2 36 ((13.)44-RU-105,4.44HR) 30639 2 37 ((13.)45-RH-105-G,35.5HR,DG,319.2,0.192)INCLUDESRH-105M30639 2 38 ((14.)46-PD-112,20.1HR) DAUGHTER AG-112 MEASURED 30639 2 39 ((14.)47-AG-112,3.13HR,DG,617.4,0.429) 30639 2 40 ((15.)51-SB-127,3.80D,DG,684.9,0.357) 30639 2 41 ((16.)53-I-131,8.041D,DG,364.5,0.820) 30639 2 42 ((17.)52-TE-132,78.HR,DG,228.2,0.885) 30639 2 43 ((18.)52-TE-132,78.HR) 30639 2 44 ((18.)53-I-132-G,2.285HR,DG,522.6,0.156) 30639 2 45 ((19.)52-TE-132,78.HR) 30639 2 46 ((19.)53-I-132-G,2.285HR,DG,630.2,0.135) 30639 2 47 ((20.)52-TE-132,78.HR) 30639 2 48 ((20.)53-I-132-G,2.285HR,DG,667.7,0.980) 30639 2 49 ((21.)52-TE-132,78.HR) 30639 2 50 ((21.)53-I-132-G,2.285HR,DG,772.7,0.750) 30639 2 51 ((22.)52-TE-132,78.HR) 30639 2 52 ((22.)53-I-132-G,2.285HR,DG,954.6,0.167) 30639 2 53 ((23.)53-I-133-G,20.8HR,DG,529.5,0.869) 30639 2 54 ((24.)52-TE-134,42.MIN) 30639 2 55 ((24.)53-I-134-G,52.6MIN,DG,847.0,0.954)INCLUDES I-134M30639 2 56 ((25.)53-I-135,6.585HR,DG,1260.5,0.286) 30639 2 57 ((26.)53-I-135,6.585HR) 30639 2 58 ((26.)54-XE-135-G,9.17HR,DG,249.7,0.903) INCL. XE-135M 30639 2 59 ((27.)56-BA-140,12.79D,DG,537.3,0.240) 30639 2 60 ((28.)56-BA-140,12.79D) 30639 2 61 ((28.)57-LA-140,40.23HR,DG,815.8,0.223) 30639 2 62 ((29.)56-BA-140,12.79D) 30639 2 63 ((29.)57-LA-140,40.23HR,DG,1596.2,0.953) 30639 2 64 ((30.)56-BA-140,12.79D) 30639 2 65 ((30.)57-LA-140,40.23HR,DG,487.0,0.46) 30639 2 66 ((31.)58-CE-141,32.53D,DG,145.4,0.48) 30639 2 67 ((32.)58-CE-143,33.0HR,DG,293.2,0.426) 30639 2 68 ASSUMED (ASSUM,92-U-238(N,F),,SIG)M.G.SOWERBY+,AERE-R-7273,197330639 2 69 ERR-ANALYS ALL ERRORS QUOTED ARE ONE STANDARD DEVIATION. THEY 30639 2 70 INCLUDE CONTRIBUTIONS FROM PEAK AREA AND DECAY CURVE 30639 2 71 ANALYSIS,GAMMA-RAY INTENSITIES,DETECTOR EFFICIENCY 30639 2 72 AND RANDOM ERROR OF THE NEUTRON FLUX.NOT INCLUDED IS 30639 2 73 THE SYSTEMATIC 3 PERCENT UNCERTAINTY IN THE NEUTRON 30639 2 74 FLUX DETERMINATION,WHICH SHOULD BE ADDED WHEN 30639 2 75 CONSIDERING ABSOLUTE FISSION YIELDS. 30639 2 76 COMMENT PRELIMINARY RESULTS OF THIS FIRST EXPERIMENT WERE 30639 2 77 REPORTED IN EARLIER PUBLICATIONS AND COMPILED IN 30639 2 78 EXFOR30267.HOWEVER, THE VALUES ARE EITHER ALTERED IN 30639 2 79 THE FINAL PUBLICATION OR WITHDRAWN IF THEY ARE 30639 2 80 SUPERSEDED BY THE SECOND AND/OR THIRD EXPERIMENT WITH 30639 2 81 MUCH BETTER DETECTOR RESOLUTION. 30639 2 82 FLAG (1.) FOR THE CALCULATION OF THE YIELD OF THE FISSION 30639 2 83 PRODUCT GIVEN THE HALF-LIFE OF ITS PRECURSOR IS 30639 2 84 ALSO USED. 30639 2 85 (2.) THE YIELD OF THE FISSION PRODUCT GIVEN IS DERIVED 30639 2 86 FROM A GAMMA-LINE OF ITS DAUGHTER PRODUCT OFTEN IN30639 2 87 EQUILIBRIUM. 30639 2 88 (3.) THE WEIGHTED AVERAGE OF ALL YIELD DATA FOR TE-132 30639 2 89 LISTED ABOVE THIS VALUE. 30639 2 90 ENDBIB 88 30639 2 91 COMMON 5 3 30639 2 92 EN EN-ERR MONIT MONIT-ERR ASSUM 30639 2 93 MEV MEV MB MB MB 30639 2 94 1.4400E+01 1.9000E-01 1.1760E+02 5.0000E-01 1.1708E+03 30639 2 95 ENDCOMMON 5 3 30639 2 96 DATA 7 35 30639 2 97 MASS ELEMENT ISOMER DATA DATA-ERR DECAY-FLAG 30639 2 98 FLAG 30639 2 99 NO-DIM NO-DIM NO-DIM PC/FIS PC/FIS NO-DIM 30639 2 100 NO-DIM 30639 2 101 9.1000E+01 3.8000E+01 3.6600E+00 4.0000E-01 1.0000E+0030639 2 102 30639 2 103 9.1000E+01 3.8000E+01 3.3600E+00 5.9000E-01 2.0000E+0030639 2 104 30639 2 105 9.1000E+01 3.8000E+01 4.3700E+00 2.3000E-01 3.0000E+0030639 2 106 30639 2 107 9.1000E+01 3.8000E+01 3.3400E+00 1.8000E-01 4.0000E+0030639 2 108 2.0000E+00 30639 2 109 9.2000E+01 3.8000E+01 3.5200E+00 1.9000E-01 5.0000E+0030639 2 110 30639 2 111 9.5000E+01 4.0000E+01 5.0700E+00 4.9000E-01 6.0000E+0030639 2 112 2.0000E+00 30639 2 113 9.7000E+01 4.0000E+01 5.0200E+00 2.5000E-01 7.0000E+0030639 2 114 2.0000E+00 30639 2 115 9.7000E+01 4.0000E+01 5.4100E+00 2.9000E-01 8.0000E+0030639 2 116 2.0000E+00 30639 2 117 9.9000E+01 4.2000E+01 5.9100E+00 1.2200E+00 9.0000E+0030639 2 118 30639 2 119 9.9000E+01 4.2000E+01 6.0700E+00 3.3000E-01 1.0000E+0130639 2 120 2.0000E+00 30639 2 121 1.0300E+02 4.4000E+01 4.6300E+00 2.6000E-01 1.1000E+0130639 2 122 30639 2 123 1.0500E+02 4.4000E+01 3.4500E+00 1.9000E-01 1.2000E+0130639 2 124 30639 2 125 1.0500E+02 4.5000E+01 0.0000E+00 2.9900E+00 1.9000E-01 1.3000E+0130639 2 126 1.0000E+00 30639 2 127 1.1200E+02 4.6000E+01 1.0230E+00 8.5000E-02 1.4000E+0130639 2 128 2.0000E+00 30639 2 129 1.2700E+02 5.1000E+01 1.4010E+00 1.5500E-01 1.5000E+0130639 2 130 30639 2 131 1.3100E+02 5.3000E+01 4.0800E+00 2.1000E-01 1.6000E+0130639 2 132 30639 2 133 1.3200E+02 5.2000E+01 4.6600E+00 2.7000E-01 1.7000E+0130639 2 134 30639 2 135 1.3200E+02 5.2000E+01 4.4300E+00 3.9000E-01 1.8000E+0130639 2 136 2.0000E+00 30639 2 137 1.3200E+02 5.2000E+01 4.4100E+00 4.0000E-01 1.9000E+0130639 2 138 2.0000E+00 30639 2 139 1.3200E+02 5.2000E+01 4.6500E+00 2.4000E-01 2.0000E+0130639 2 140 2.0000E+00 30639 2 141 1.3200E+02 5.2000E+01 4.5300E+00 2.6000E-01 2.1000E+0130639 2 142 2.0000E+00 30639 2 143 1.3200E+02 5.2000E+01 4.7100E+00 2.6000E-01 2.2000E+0130639 2 144 2.0000E+00 30639 2 145 1.3200E+02 5.2000E+01 4.6000E+00 1.1700E-01 30639 2 146 3.0000E+00 30639 2 147 1.3300E+02 5.3000E+01 0.0000E+00 6.1300E+00 3.2000E-01 2.3000E+0130639 2 148 30639 2 149 1.3400E+02 5.3000E+01 0.0000E+00 6.3400E+00 8.4000E-01 2.4000E+0130639 2 150 1.0000E+00 30639 2 151 1.3500E+02 5.3000E+01 5.2500E+00 2.9000E-01 2.5000E+0130639 2 152 30639 2 153 1.3500E+02 5.3000E+01 5.0400E+00 2.9000E-01 2.6000E+0130639 2 154 2.0000E+00 30639 2 155 1.3500E+02 5.4000E+01 0.0000E+00 5.3400E+00 3.0000E-01 2.6000E+0130639 2 156 1.0000E+00 30639 2 157 1.4000E+02 5.6000E+01 4.8100E+00 2.9000E-01 2.7000E+0130639 2 158 30639 2 159 1.4000E+02 5.6000E+01 4.8900E+00 2.7000E-01 2.8000E+0130639 2 160 2.0000E+00 30639 2 161 1.4000E+02 5.6000E+01 4.3200E+00 2.2000E-01 2.9000E+0130639 2 162 2.0000E+00 30639 2 163 1.4000E+02 5.6000E+01 4.3900E+00 2.4000E-01 3.0000E+0130639 2 164 2.0000E+00 30639 2 165 1.4000E+02 5.7000E+01 4.4400E+00 3.2000E-01 3.0000E+0130639 2 166 1.0000E+00 30639 2 167 1.4100E+02 5.8000E+01 4.4600E+00 3.0000E-01 3.1000E+0130639 2 168 30639 2 169 1.4300E+02 5.8000E+01 3.6000E+00 1.9000E-01 3.2000E+0130639 2 170 30639 2 171 ENDDATA 74 30639 2 172 ENDSUBENT 7 30639 299999 SUBENT 30639003 841217 30639 3 1 BIB 12 89 30639 3 2 EXP-YEAR (71) SECOND EXPERIMENT,2 SAMPLES 30639 3 3 REACTION (92-U-238(N,F)ELEM/MASS,CUM,FY) SHORT LIVED PRODUCTS 30639 3 4 INC-SOURCE NEUTRON FLUX=(2.10+-0.05)*10**8 N/(S*CM**2) RANDOM 30639 3 5 ERROR,OR +-3 PERCENT SYSTEMATIC ERROR, 30639 3 6 IRRADIATION TIME=5 MIN FOR EACH SAMPLE 30639 3 7 NUMBER OF FISSION EVENTS=3.92*10**8 FOR EACH SAMPLE 30639 3 8 SAMPLE 2490.4 GRAMS,THICKNESS=1.47 MM OR 921.4 MG/CM**2, 30639 3 9 DIAMETER=18.6 MM (BOTH SAMPLES) 30639 3 10 DETECTOR (GELI).20 CCM, 4000 CHANNEL PULSE HEIGHT ANALYSER, 30639 3 11 RESOLUTION AT 662 KEV = 4.63 KEV. 30639 3 12 ANALYSIS 50 GAMMA SPECTRA WERE RECORDED AND ANALYSED BY AN 30639 3 13 IMPROVED GRAPHICAL-NUMERICAL METHOD USING REAL LINE 30639 3 14 SHAPES.COMPLETE DECAY CURVES FROM 2.5 MINUTES TO 30639 3 15 19.5 DAYS AFTER IRRADIATION WERE ANALYSED. 30639 3 16 MONITOR (29-CU-63(N,2N)29-CU-62,,SIG)USING 4-PI BETA COUNTING 30639 3 17 MONIT-REF (,Y.KANDA+,C,68WASH,1,193,68) 30639 3 18 DECAY-DATA PARENT DAUGHTER RELATIONSHIPS INDICATED BY FLAGS 30639 3 19 ((1.)34-SE-83-G,22.5MIN,DG,356.6,0.686) 30639 3 20 ((2.)36-KR-85-M,4.48HR,DG,151.3,0.761) 30639 3 21 ((3.)36-KR-87,76.0MIN,DG,402.7,0.483) 30639 3 22 ((4.)36-KR-88,2.80HR,DG,196.1,0.272) 30639 3 23 ((5.)36-KR-89,3.16MIN,DG,220.9,0.25) 30639 3 24 ((6.)36-KR-89,3.16MIN) FOR DAUGHTER RB-89 30639 3 25 ((6.)37-RB-89,15.2MIN,DG,1031.9,0.641) 30639 3 26 ((7.)38-SR-91,9.48HR,DG,1024.3,0.334) 30639 3 27 ((8.)38-SR-92,2.71HR,DG,1383.9,0.9) 30639 3 28 ((9.)38-SR-93,7.5MIN,DG,590.9,0.61)SEE FLAG (4.) 30639 3 29 ((10.)40-ZR-97,16.8HR) FOR DAUGHTER NB-97-G,M 30639 3 30 ((10.)41-NB-97-G,73.6MIN,DG,658.2,0.981) 30639 3 31 ((11.)42-MO-101,14.6MIN,DG,590.8,0.194) 30639 3 32 ((12.)42-MO-101,14.6MIN) FOR DAUGHTER TC-101 30639 3 33 ((12.)43-TC-101,14.MIN,DG,306.8,0.875) 30639 3 34 ((13.)43-TC-104,18.0MIN,DG,357.8,0.844) 30639 3 35 ((14.)44-RU-105,4.44HR,DG,724.2,0.49) 30639 3 36 ((15.)51-SB-131,23.0MIN) 30639 3 37 ((15.)52-TE-131-G,25.0MIN,DG,149.8,0.677) 30639 3 38 ((16.)51-SB-131,23.0MIN) 30639 3 39 ((16.)52-TE-131-M,30.HR,DG,149.8,0.364) 30639 3 40 ((17.)52-TE-132,78.HR,DG,228.2,0.885) 30639 3 41 ((18.)52-TE-132,78.HR) FOR DAUGHTER I-132 30639 3 42 ((18.)53-I-132-G,2.285HR,DG,667.7,0.980) 30639 3 43 ((19.)53-I-133-G,20.8HR,DG,529.5,0.869) 30639 3 44 ((20.)52-TE-134,42.MIN,DG,210.8,0.222) 30639 3 45 ((21.)52-TE-134,42.MIN) FOR DAUGHTER I-134 30639 3 46 ((21.)53-I-134-G,52.6MIN,DG,847.0,0.954)INCLUDES I-134M30639 3 47 ((22.)52-TE-134,42.MIN) FOR DAUGHTER I-134 30639 3 48 ((22.)53-I-134-G,52.6MIN,DG,884.1,0.653)INCLUDES I-134M30639 3 49 ((23.)53-I-134-G,52.6MIN,DG,847.0,0.954)INCLUDES I-134M30639 3 50 ((24.)53-I-134-G,52.6MIN,DG,884.1,0.653)INCLUDES I-134M30639 3 51 ((25.)53-I-135,6.585HR,DG,1260.5,0.286) 30639 3 52 ((26.)53-I-135,6.585HR) FOR DAUGHTER XE-135 30639 3 53 ((26.)54-XE-135-G,9.17HR,DG,249.7,0.903) INCL. XE-135M 30639 3 54 ((27.)54-XE-138,14.2MIN) FOR DAUGHTER CS-138-G 30639 3 55 ((27.)55-CS-138-G,32.2MIN,DG,1435.7,0.750) 30639 3 56 ((28.)56-BA-139,83.3MIN,DG,165.8,0.218) 30639 3 57 ((29.)57-LA-142,92.4MIN,DG,641.2,0.475) 30639 3 58 ((30.)58-CE-143,33.0HR,DG,293.2,0.426) 30639 3 59 ((31.)58-CE-146,14.2MIN,DG,218.3,0.214) 30639 3 60 ((32.)60-ND-149,1.73HR,DG,211.3,0.23) 30639 3 61 ASSUMED (ASSUM,92-U-238(N,F),,SIG)M.G.SOWERBY+,AERE-R-7273,197330639 3 62 ERR-ANALYS ALL ERRORS QUOTED ARE ONE STANDARD DEVIATION. THEY 30639 3 63 INCLUDE CONTRIBUTIONS FROM PEAK AREA AND DECAY CURVE 30639 3 64 ANALYSIS,GAMMA-RAY INTENSITIES,DETECTOR EFFICIENCY 30639 3 65 AND RANDOM ERROR OF THE NEUTRON FLUX.NOT INCLUDED IS 30639 3 66 THE SYSTEMATIC 3 PERCENT UNCERTAINTY IN THE NEUTRON 30639 3 67 FLUX DETERMINATION,WHICH SHOULD BE ADDED WHEN 30639 3 68 CONSIDERING ABSOLUTE FISSION YIELDS. 30639 3 69 FLAG (1.) FOR THE CALCULATION OF THE YIELD OF THE FISSION 30639 3 70 PRODUCT GIVEN THE HALF-LIFE OF ITS PRECURSOR IS 30639 3 71 ALSO USED. 30639 3 72 (2.) THE YIELD OF THE FISSION PRODUCT GIVEN IS DERIVED 30639 3 73 FROM A GAMMA-LINE OF ITS DAUGHTER PRODUCT OFTEN IN30639 3 74 EQUILIBRIUM. 30639 3 75 (3.) THE WEIGHTED AVERAGE OF ALL YIELD DATA FOR TE-132 30639 3 76 LISTED ABOVE THIS VALUE. 30639 3 77 (4.) THIS IS NOT THE VALUE MEASURED IN THIS EXPERIMENT 30639 3 78 FOR SR-93,BUT THE CUMULATIVE YIELD OF Y-93 FROM 30639 3 79 THE 3RD EXPERIMENT (SUBENTRY 4).IN THIS SECOND 30639 3 80 EXPERIMENT THE AUTHORS OBTAINED A VALUE OF 2.51+- 30639 3 81 0.23 FOR THE YIELD OF SR-93,USING ARBITRARILY 100 30639 3 82 PERCENT INTENSITY OF THE 590.9 KEV GAMMA-RAY IN 30639 3 83 THE DECAY OF SR-93 (AS NO ABSOLUTE INTENSITY VALUE30639 3 84 WAS FOUND IN LITERATURE).IF THE ABUNDANCE OF THIS 30639 3 85 GAMMA RAY IS KNOWN, THE CORRECT ABSOLUTE CUMU- 30639 3 86 LATIVE YIELD CAN BE CALCULATED USING THE 'YIELD' 30639 3 87 VALUE GIVEN ABOVE. FROM MEASURED YIELD RATIO 30639 3 88 SR-93/Y-93=2.51/4.10=0.61 THE AUTHORS DEDUCE AN 30639 3 89 ABSOLUTE INTENSITY OF 61+-8 PERCENT FOR THE 590.9 30639 3 90 KEV GAMMA RAY OF SR-93. 30639 3 91 ENDBIB 89 30639 3 92 COMMON 5 3 30639 3 93 EN EN-ERR MONIT MONIT-ERR ASSUM 30639 3 94 MEV MEV MB MB MB 30639 3 95 1.4400E+01 2.5000E-01 4.9700E+02 1.3000E+01 1.1708E+03 30639 3 96 ENDCOMMON 5 3 30639 3 97 DATA 7 37 30639 3 98 MASS ELEMENT ISOMER DATA DATA-ERR DECAY-FLAG 30639 3 99 FLAG 30639 3 100 NO-DIM NO-DIM NO-DIM PC/FIS PC/FIS NO-DIM 30639 3 101 NO-DIM 30639 3 102 8.3000E+01 3.4000E+01 0.0000E+00 2.6000E-01 5.2000E-02 1.0000E+0030639 3 103 30639 3 104 8.5000E+01 3.6000E+01 1.0000E+00 1.0230E+00 4.6000E-02 2.0000E+0030639 3 105 30639 3 106 8.7000E+01 3.6000E+01 1.8910E+00 8.3000E-02 3.0000E+0030639 3 107 30639 3 108 8.8000E+01 3.6000E+01 1.8260E+00 7.0000E-02 4.0000E+0030639 3 109 30639 3 110 8.9000E+01 3.6000E+01 3.0700E+00 6.4000E-01 5.0000E+0030639 3 111 30639 3 112 8.9000E+01 3.7000E+01 2.8100E+00 1.4000E-01 6.0000E+0030639 3 113 1.0000E+00 30639 3 114 9.1000E+01 3.8000E+01 4.3800E+00 1.5000E-01 7.0000E+0030639 3 115 30639 3 116 9.2000E+01 3.8000E+01 3.8600E+00 1.2000E-01 8.0000E+0030639 3 117 30639 3 118 9.3000E+01 3.8000E+01 4.1000E+00 4.0000E-01 9.0000E+0030639 3 119 4.0000E+00 30639 3 120 9.7000E+01 4.0000E+01 5.0900E+00 1.4000E-01 1.0000E+0130639 3 121 2.0000E+00 30639 3 122 1.0100E+02 4.2000E+01 5.4800E+00 7.3000E-01 1.1000E+0130639 3 123 30639 3 124 1.0100E+02 4.2000E+01 5.7100E+00 2.7000E-01 1.2000E+0130639 3 125 2.0000E+00 30639 3 126 1.0100E+02 4.3000E+01 5.9700E+00 4.1000E-01 1.2000E+0130639 3 127 1.0000E+00 30639 3 128 1.0400E+02 4.3000E+01 3.5900E+00 1.5000E-01 1.3000E+0130639 3 129 30639 3 130 1.0500E+02 4.4000E+01 3.0100E+00 1.3000E-01 1.4000E+0130639 3 131 30639 3 132 1.3100E+02 5.1000E+01 2.5400E+00 1.4000E-01 1.5000E+0130639 3 133 2.0000E+00 30639 3 134 1.3100E+02 5.2000E+01 0.0000E+00 3.8000E+00 1.6000E-01 1.5000E+0130639 3 135 1.0000E+00 30639 3 136 1.3100E+02 5.2000E+01 1.0000E+00 3.1100E-01 1.2500E-01 1.6000E+0130639 3 137 1.0000E+00 30639 3 138 1.3200E+02 5.2000E+01 4.8700E+00 2.1000E-01 1.7000E+0130639 3 139 30639 3 140 1.3200E+02 5.2000E+01 4.5600E+00 1.8000E-01 1.8000E+0130639 3 141 2.0000E+00 30639 3 142 1.3200E+02 5.2000E+01 4.6910E+00 1.3700E-01 30639 3 143 3.0000E+00 30639 3 144 1.3300E+02 5.3000E+01 6.0000E+00 3.0000E-01 1.9000E+0130639 3 145 30639 3 146 1.3400E+02 5.2000E+01 4.7600E+00 3.1000E-01 2.0000E+0130639 3 147 30639 3 148 1.3400E+02 5.2000E+01 4.4200E+00 1.8000E-01 2.1000E+0130639 3 149 2.0000E+00 30639 3 150 1.3400E+02 5.2000E+01 4.3600E+00 8.0000E-01 2.2000E+0130639 3 151 2.0000E+00 30639 3 152 1.3400E+02 5.3000E+01 0.0000E+00 5.8500E+00 1.8000E-01 2.3000E+0130639 3 153 30639 3 154 1.3400E+02 5.3000E+01 0.0000E+00 5.8900E+00 9.6000E-01 2.4000E+0130639 3 155 30639 3 156 1.3500E+02 5.3000E+01 5.4800E+00 2.2000E-01 2.5000E+0130639 3 157 30639 3 158 1.3500E+02 5.3000E+01 5.3600E+00 2.2000E-01 2.6000E+0130639 3 159 2.0000E+00 30639 3 160 1.3500E+02 5.4000E+01 0.0000E+00 5.6800E+00 2.2000E-01 2.6000E+0130639 3 161 1.0000E+00 30639 3 162 1.3800E+02 5.4000E+01 4.2600E+00 4.4000E-01 2.7000E+0130639 3 163 2.0000E+00 30639 3 164 1.3800E+02 5.5000E+01 0.0000E+00 4.5100E+00 2.3000E-01 2.7000E+0130639 3 165 1.0000E+00 30639 3 166 1.3900E+02 5.6000E+01 5.1300E+00 2.5000E-01 2.8000E+0130639 3 167 30639 3 168 1.4200E+02 5.7000E+01 4.1900E+00 1.4000E-01 2.9000E+0130639 3 169 30639 3 170 1.4300E+02 5.8000E+01 3.9800E+00 1.7000E-01 3.0000E+0130639 3 171 30639 3 172 1.4600E+02 5.8000E+01 1.9190E+00 2.3400E-01 3.1000E+0130639 3 173 30639 3 174 1.4900E+02 6.0000E+01 1.2900E+00 1.3700E-01 3.2000E+0130639 3 175 30639 3 176 ENDDATA 78 30639 3 177 ENDSUBENT 7 30639 399999 SUBENT 30639004 841217 30639 4 1 BIB 12 91 30639 4 2 EXP-YEAR (73) THIRD EXPERIMENT,REPETITION OF FIRST EXPERIMENT 30639 4 3 WITH BETTER RESOLUTION. 30639 4 4 REACTION (92-U-238(N,F)ELEM/MASS,CUM,FY) LONG LIVED PRODUCTS 30639 4 5 INC-SOURCE NEUTRON FLUX=(4.91+-0.11)*10**9 N/(S*CM**2) RANDOM 30639 4 6 ERROR,OR +-3 PERCENT SYSTEMATIC ERROR 30639 4 7 IRRADIATION TIME = 1.25 HOURS 30639 4 8 NUMBER OF FISSION EVENTS = 5.56*10**10. 30639 4 9 SAMPLE 996.7 GRAMS, THICKNESS=0.668 MM OR 351.5 MG/CM**2, 30639 4 10 DIAMETER=19.0 MM 30639 4 11 DETECTOR (GELI).40 CCM, 4000 CHANNEL PULSE HEIGHT ANALYSER, 30639 4 12 RESOLUTION AT 662 KEV = 3.36 KEV. 30639 4 13 ANALYSIS 16 GAMMA SPECTRA WERE RECORDED AND ANALYSED BY AN 30639 4 14 IMPROVED GRAPHICAL-NUMERICAL METHOD USING REAL LINE 30639 4 15 SHAPES.COMPLETE DECAY CURVES FROM 41 HRS TO 412 DAYS 30639 4 16 AFTER IRRADIATION WERE ANALYSED. 30639 4 17 MONITOR (13-AL-27(N,A)11-NA-24,,SIG) USING 4-PI BETA COUNTING. 30639 4 18 MONIT-REF (,H.VONACH+,J,ZP,273,155,70) 30639 4 19 DECAY-DATA PARENT DAUGHTER RELATIONSHIPS INDICATED BY FLAGS 30639 4 20 ((1.)38-SR-91,9.48HR,DG,749.8,0.231) 30639 4 21 ((2.)38-SR-91,9.48HR,DG,1024.3,0.334) 30639 4 22 ((3.)38-SR-91,9.48HR) FOR DAUGHTER Y-91-M 30639 4 23 ((3.)39-Y-91-M,49.7MIN,DG,555.6,0.558) 30639 4 24 ((4.)39-Y-93,10.2HR,DG,267.0,0.064) 30639 4 25 ((5.)40-ZR-95,62.5D,DG,724.2,0.438) 30639 4 26 ((6.)40-ZR-95,62.5D,DG,756.7,0.544) 30639 4 27 ((7.)40-ZR-97,16.8HR) FOR DAUGHTER NB-97-G,M 30639 4 28 ((7.)41-NB-97-G,73.6MIN,DG,658.2,0.981) 30639 4 29 ((8.)40-ZR-97,16.8HR) FOR DAUGHTER NB-97-G,M 30639 4 30 ((8.)41-NB-97-M,54.SEC,DG,743.4,0.933) 30639 4 31 ((9.)42-MO-99,66.02HR,DG,181.0,0.059) 30639 4 32 ((10.)42-MO-99,66.02HR,DG,739.6,0.120) 30639 4 33 ((11.)42-MO-99,66.02HR) FOR DAUGHTER TC-99-M 30639 4 34 ((11.)43-TC-99-M,6.02HR,DG,140.4,0.810) 30639 4 35 ((12.)44-RU-103,39.6D,DG,497.1,0.89) 30639 4 36 ((13.)44-RU-105,4.44HR) FOR DAUGHTER RH-105-M+G 30639 4 37 ((13.)45-RH-105-G,35.5HR,DG,319.2,0.192)INCLUDESRH-105M30639 4 38 ((14.)44-RU-106,369.D) 30639 4 39 ((14.)45-RH-106-G,,DG,621.8,0.098)EQUILIBRIUM W. RU-10630639 4 40 ((15.)46-PD-112,20.1HR) DAUGHTER AG-112 MEASURED 30639 4 41 ((15.)47-AG-112,3.13HR,DG,617.4,0.429) 30639 4 42 ((16.)48-CD-115-G,53.5HR) DAUGHTER IN-115-M MEASURED 30639 4 43 ((16.)49-IN-115-M,4.50HR,DG,336.2,0.470) 30639 4 44 ((17.)51-SB-125,3.72YR,DG,427.9,0.304) 30639 4 45 ((18.)51-SB-125,3.72YR,DG,600.6,0.181) 30639 4 46 ((19.)51-SB-127,3.80D,DG,473.2,0.250) 30639 4 47 ((20.)51-SB-127,3.80D,DG,684.9,0.357) 30639 4 48 ((21.)52-TE-129-M,33.4D,DG,459.6,0.090) 30639 4 49 ((22.)51-SB-131,23.0MIN) 30639 4 50 ((22.)52-TE-131-M,30.HR,DG,149.8,0.364) 30639 4 51 ((23.)53-I-131,8.041D,DG,364.5,0.820) 30639 4 52 ((24.)52-TE-132,78.HR,DG,228.2,0.885) 30639 4 53 ((25.)52-TE-132,78.HR) FOR DAUGHTER I-132 30639 4 54 ((25.)53-I-132-G,2.285HR,DG,522.6,0.156) 30639 4 55 ((26.)52-TE-132,78.HR) FOR DAUGHTER I-132 30639 4 56 ((26.)53-I-132-G,2.285HR,DG,630.2,0.135) 30639 4 57 ((27.)52-TE-132,78.HR) FOR DAUGHTER I-132 30639 4 58 ((27.)53-I-132-G,2.285HR,DG,667.7,0.980) 30639 4 59 ((28.)52-TE-132,78.HR) FOR DAUGHTER I-132 30639 4 60 ((28.)53-I-132-G,2.285HR,DG,772.7,0.750) 30639 4 61 ((29.)52-TE-132,78.HR) FOR DAUGHTER I-132 30639 4 62 ((29.)53-I-132-G,2.285HR,DG,954.6,0.167) 30639 4 63 ((30.)53-I-133-G,20.8HR,DG,529.5,0.869) 30639 4 64 ((31.)53-I-133-G,20.8HR,DG,875.3,0.048) 30639 4 65 ((32.)53-I-135,6.585HR) FOR DAUGHTER XE-135 30639 4 66 ((33.)55-CS-137,30.1YR) 30639 4 67 ((33.)56-BA-137-M,,DG,661.6,0.85) EQUILIBRIUM W. CS-13730639 4 68 ((34.)56-BA-140,12.79D,DG,537.3,0.240) 30639 4 69 ((35.)56-BA-140,12.79D) FOR DAUGHTER LA-140 30639 4 70 ((35.)57-LA-140,40.23HR,DG,815.8,0.223) 30639 4 71 ((36.)56-BA-140,12.79D) FOR DAUGHTER LA-140 30639 4 72 ((36.)57-LA-140,40.23HR,DG,487.0,0.46) 30639 4 73 ((37.)58-CE-141,32.53D,DG,145.4,0.48) 30639 4 74 ((38.)58-CE-143,33.0HR,DG,293.2,0.426) 30639 4 75 ((39.)58-CE-144,284.4D,DG,133.5,0.107) 30639 4 76 ((40.)60-ND-147,10.99D,DG,531.0,0.131) 30639 4 77 ASSUMED (ASSUM,92-U-238(N,F),,SIG)M.G.SOWERBY+,AERE-R-7273,197330639 4 78 ERR-ANALYS ALL ERRORS QUOTED ARE ONE STANDARD DEVIATION. THEY 30639 4 79 INCLUDE CONTRIBUTIONS FROM PEAK AREA AND DECAY CURVE 30639 4 80 ANALYSIS,GAMMA-RAY INTENSITIES,DETECTOR EFFICIENCY 30639 4 81 AND RANDOM ERROR OF THE NEUTRON FLUX.NOT INCLUDED IS 30639 4 82 THE SYSTEMATIC 3 PERCENT UNCERTAINTY IN THE NEUTRON 30639 4 83 FLUX DETERMINATION,WHICH SHOULD BE ADDED WHEN 30639 4 84 CONSIDERING ABSOLUTE FISSION YIELDS. 30639 4 85 FLAG (1.) FOR THE CALCULATION OF THE YIELD OF THE FISSION 30639 4 86 PRODUCT GIVEN THE HALF-LIFE OF ITS PRECURSOR IS 30639 4 87 ALSO USED. 30639 4 88 (2.) THE YIELD OF THE FISSION PRODUCT GIVEN IS DERIVED 30639 4 89 FROM A GAMMA-LINE OF ITS DAUGHTER PRODUCT OFTEN IN30639 4 90 EQUILIBRIUM. 30639 4 91 (3.) THE WEIGHTED AVERAGE OF ALL YIELD DATA FOR TE-132 30639 4 92 LISTED ABOVE THIS VALUE. 30639 4 93 ENDBIB 91 30639 4 94 COMMON 5 3 30639 4 95 EN EN-ERR MONIT MONIT-ERR ASSUM 30639 4 96 MEV MEV MB MB MB 30639 4 97 1.4540E+01 3.1000E-01 1.1490E+02 5.0000E-01 1.1865E+03 30639 4 98 ENDCOMMON 5 3 30639 4 99 DATA 7 41 30639 4 100 MASS ELEMENT ISOMER DATA DATA-ERR DECAY-FLAG 30639 4 101 FLAG 30639 4 102 NO-DIM NO-DIM NO-DIM PC/FIS PC/FIS NO-DIM 30639 4 103 NO-DIM 30639 4 104 9.1000E+01 3.8000E+01 4.3900E+00 3.4000E-01 1.0000E+0030639 4 105 30639 4 106 9.1000E+01 3.8000E+01 4.2200E+00 1.5000E-01 2.0000E+0030639 4 107 30639 4 108 9.1000E+01 3.8000E+01 3.7600E+00 1.2000E-01 3.0000E+0030639 4 109 2.0000E+00 30639 4 110 9.3000E+01 3.9000E+01 4.1000E+00 4.0000E-01 4.0000E+0030639 4 111 30639 4 112 9.5000E+01 4.0000E+01 4.6100E+00 1.3000E-01 5.0000E+0030639 4 113 30639 4 114 9.5000E+01 4.0000E+01 4.6300E+00 1.3000E-01 6.0000E+0030639 4 115 30639 4 116 9.7000E+01 4.0000E+01 5.0600E+00 1.6000E-01 7.0000E+0030639 4 117 2.0000E+00 30639 4 118 9.7000E+01 4.0000E+01 5.2900E+00 2.6000E-01 8.0000E+0030639 4 119 2.0000E+00 30639 4 120 9.9000E+01 4.2000E+01 5.8200E+00 2.6000E-01 9.0000E+0030639 4 121 30639 4 122 9.9000E+01 4.2000E+01 5.8000E+00 4.5000E-01 1.0000E+0130639 4 123 30639 4 124 9.9000E+01 4.2000E+01 5.6400E+00 1.7000E-01 1.1000E+0130639 4 125 2.0000E+00 30639 4 126 1.0300E+02 4.4000E+01 4.5100E+00 1.3000E-01 1.2000E+0130639 4 127 30639 4 128 1.0500E+02 4.5000E+01 0.0000E+00 3.1500E+00 1.4000E-01 1.3000E+0130639 4 129 1.0000E+00 30639 4 130 1.0600E+02 4.4000E+01 2.5400E+00 1.5000E-01 1.4000E+0130639 4 131 2.0000E+00 30639 4 132 1.1200E+02 4.6000E+01 1.1100E+00 6.6000E-02 1.5000E+0130639 4 133 2.0000E+00 30639 4 134 1.1500E+02 4.8000E+01 8.4300E-01 4.8000E-02 1.6000E+0130639 4 135 2.0000E+00 30639 4 136 1.2500E+02 5.1000E+01 1.1640E+00 8.3000E-02 1.7000E+0130639 4 137 30639 4 138 1.2500E+02 5.1000E+01 1.3370E+00 1.4900E-01 1.8000E+0130639 4 139 30639 4 140 1.2700E+02 5.1000E+01 1.4130E+00 4.7000E-02 1.9000E+0130639 4 141 30639 4 142 1.2700E+02 5.1000E+01 1.4710E+00 6.9000E-02 2.0000E+0130639 4 143 30639 4 144 1.2900E+02 5.2000E+01 1.0000E+00 5.2600E-01 5.1000E-02 2.1000E+0130639 4 145 30639 4 146 1.3100E+02 5.2000E+01 1.0000E+00 3.6300E-01 3.6000E-02 2.2000E+0130639 4 147 1.0000E+00 30639 4 148 1.3100E+02 5.3000E+01 4.0100E+00 1.1000E-01 2.3000E+0130639 4 149 30639 4 150 1.3200E+02 5.2000E+01 4.6600E+00 1.5000E-01 2.4000E+0130639 4 151 30639 4 152 1.3200E+02 5.2000E+01 4.7700E+00 1.9000E-01 2.5000E+0130639 4 153 2.0000E+00 30639 4 154 1.3200E+02 5.2000E+01 4.6200E+00 1.4000E-01 2.6000E+0130639 4 155 2.0000E+00 30639 4 156 1.3200E+02 5.2000E+01 4.5800E+00 1.8000E-01 2.7000E+0130639 4 157 2.0000E+00 30639 4 158 1.3200E+02 5.2000E+01 4.6400E+00 1.6000E-01 2.8000E+0130639 4 159 2.0000E+00 30639 4 160 1.3200E+02 5.2000E+01 4.6400E+00 1.6000E-01 2.9000E+0130639 4 161 2.0000E+00 30639 4 162 1.3200E+02 5.2000E+01 4.6470E+00 6.6000E-02 30639 4 163 3.0000E+00 30639 4 164 1.3300E+02 5.3000E+01 5.6500E+00 1.6000E-01 3.0000E+0130639 4 165 30639 4 166 1.3300E+02 5.3000E+01 5.6800E+00 3.5000E-01 3.1000E+0130639 4 167 30639 4 168 1.3500E+02 5.3000E+01 5.1400E+00 2.7000E-01 3.2000E+0130639 4 169 30639 4 170 1.3700E+02 5.5000E+01 5.2100E+00 3.6000E-01 3.3000E+0130639 4 171 2.0000E+00 30639 4 172 1.4000E+02 5.6000E+01 4.7100E+00 1.3000E-01 3.4000E+0130639 4 173 30639 4 174 1.4000E+02 5.6000E+01 4.7900E+00 1.4000E-01 3.5000E+0130639 4 175 2.0000E+00 30639 4 176 1.4000E+02 5.6000E+01 4.4600E+00 1.3000E-01 3.6000E+0130639 4 177 2.0000E+00 30639 4 178 1.4100E+02 5.8000E+01 4.3600E+00 1.6000E-01 3.7000E+0130639 4 179 30639 4 180 1.4300E+02 5.8000E+01 3.8800E+00 1.2000E-01 3.8000E+0130639 4 181 30639 4 182 1.4400E+02 5.8000E+01 3.3900E+00 2.2000E-01 3.9000E+0130639 4 183 30639 4 184 1.4700E+02 6.0000E+01 2.3000E+00 1.0000E-01 4.0000E+0130639 4 185 30639 4 186 ENDDATA 86 30639 4 187 ENDSUBENT 7 30639 499999 SUBENT 30639005 840912 30639 5 1 BIB 4 30 30639 5 2 REACTION (92-U-238(N,F)ELEM/MASS,CUM,FY) FINAL RESULT OF ALL 3 30639 5 3 EXPERIMENTS 30639 5 4 ERR-ANALYS THE ERRORS ARE ONE STANDARD DEVIATION CALCULATED FROM 30639 5 5 THE ERRORS OF INDIVIDUAL MEASUREMENTS AS COMPILED IN 30639 5 6 THE PRECEDING SUBENTRIES.FOR THE TOTAL ERROR OF 30639 5 7 ABSOLUTE YIELDS A 3 PERCENT SYSTEMATIC UNCERTAINTY IN 30639 5 8 THE NEUTRON FLUX DETERMINATION HAS TO BE ADDED. 30639 5 9 FLAG DATA FOR CHARGE DISTRIBUTION AND DECAY BRANCHING RATIOS30639 5 10 USED IN THE ANALYSIS ARE TAKEN FROM M.E.MEEK AND 30639 5 11 B.F.RIDER,NEDO-12154-1,1974. 30639 5 12 (1.) INDIVIDUAL RESULTS FOR PARENT AND DAUGHTER ARE 30639 5 13 AVERAGED TOGETHER AS CHARGE DISTRIBUTION INDICATES30639 5 14 ZERO INDEPENDENT YIELD FOR DAUGHTER. 30639 5 15 (2.) INCLUDED IN THE AVERAGE CUMULATIVE YIELD OF I-131 30639 5 16 IS A VALUE OF 4.09+-0.17 DERIVED FROM THE SUM OF 30639 5 17 THE CUMULATIVE YIELD OF SB-131(LISTED ABOVE) AND 30639 5 18 THE INDEPENDENT YIELDS OF THE TE-131 ISOMERS 30639 5 19 (SUBENTRY 9) 30639 5 20 (3.) FOR TE-132,THE YIELD VALUE GIVEN HERE IS DERIVED 30639 5 21 FROM THE WEIGHTED AVERAGES OBTAINED IN EACH 30639 5 22 EXPERIMENT (IDENTIFIED BY FLAG 3. IN SUBENTRIES 30639 5 23 2,3 AND 4). 30639 5 24 (4.) A VALUE CALCULATED AS CUMULATIVE YIELD OF PARENT 30639 5 25 PLUS INDEPENDENT YIELD OF PRODUCT (DERIVED FROM 30639 5 26 CHARGE DISTRIBUTION) IS INCLUDED IN THE AVERAGE. 30639 5 27 STATUS (DEP,30639002) AND 30639 5 28 (DEP,30639003) AND 30639 5 29 (DEP,30639004) AS WEIGHTED AVERAGE OF ALL INDIVIDUAL 30639 5 30 RESULTS OF THE 3 EXPERIMENTS COMPILED IN THE 30639 5 31 PREVIOUS SUBENTRIES. 30639 5 32 ENDBIB 30 30639 5 33 COMMON 2 3 30639 5 34 EN-MIN EN-MAX 2 30639 5 35 MEV MEV 30639 5 36 1.4400E+01 1.4520E+01 30639 5 37 ENDCOMMON 2 3 30639 5 38 DATA 6 47 30639 5 39 MASS ELEMENT ISOMER DATA DATA-ERR FLAG 30639 5 40 NO-DIM NO-DIM NO-DIM PC/FIS PC/FIS NO-DIM 30639 5 41 8.3000E+01 3.4000E+01 0.0000E+00 2.6000E-01 5.2000E-02 30639 5 42 8.5000E+01 3.6000E+01 1.0000E+00 1.0230E+00 4.6000E-02 30639 5 43 8.7000E+01 3.6000E+01 1.8910E+00 8.3000E-02 30639 5 44 8.8000E+01 3.6000E+01 1.8260E+00 7.0000E-02 30639 5 45 8.9000E+01 3.6000E+01 3.0700E+00 6.4000E-01 30639 5 46 8.9000E+01 3.7000E+01 2.8100E+00 1.4000E-01 30639 5 47 9.1000E+01 3.8000E+01 3.9800E+00 1.6000E-01 30639 5 48 9.2000E+01 3.8000E+01 3.7800E+00 1.0000E-01 30639 5 49 9.3000E+01 3.9000E+01 4.1000E+00 4.0000E-01 30639 5 50 9.5000E+01 4.0000E+01 4.6400E+00 9.0000E-02 30639 5 51 9.7000E+01 4.0000E+01 5.1200E+00 9.0000E-02 30639 5 52 9.9000E+01 4.2000E+01 5.7600E+00 1.2000E-01 30639 5 53 1.0100E+02 4.2000E+01 5.7600E+00 2.2000E-01 1.0000E+0030639 5 54 1.0100E+02 4.3000E+01 5.7600E+00 2.2000E-01 1.0000E+0030639 5 55 1.0300E+02 4.4000E+01 4.5300E+00 1.2000E-01 30639 5 56 1.0400E+02 4.3000E+01 3.5900E+00 1.5000E-01 30639 5 57 1.0500E+02 4.4000E+01 3.1200E+00 8.0000E-02 1.0000E+0030639 5 58 1.0500E+02 4.5000E+01 3.1200E+00 8.0000E-02 1.0000E+0030639 5 59 1.0600E+02 4.4000E+01 2.5400E+00 1.5000E-01 30639 5 60 1.1200E+02 4.6000E+01 1.0770E+00 5.2000E-02 30639 5 61 1.1500E+02 4.8000E+01 0.0000E+00 8.4300E-01 4.8000E-02 30639 5 62 1.2500E+02 5.1000E+01 1.2050E+00 7.3000E-02 30639 5 63 1.2700E+02 5.1000E+01 1.4300E+00 3.8000E-02 30639 5 64 1.2900E+02 5.2000E+01 1.0000E+00 5.2600E-01 5.1000E-02 30639 5 65 1.3100E+02 5.1000E+01 2.5400E+00 1.4000E-01 30639 5 66 1.3100E+02 5.2000E+01 0.0000E+00 3.8000E+00 1.6000E-01 30639 5 67 1.3100E+02 5.2000E+01 1.0000E+00 3.5900E-01 3.5000E-02 30639 5 68 1.3100E+02 5.3000E+01 4.0400E+00 8.0000E-02 2.0000E+0030639 5 69 1.3200E+02 5.2000E+01 4.6440E+00 5.3000E-02 3.0000E+0030639 5 70 1.3300E+02 5.3000E+01 0.0000E+00 5.7800E+00 1.2000E-01 30639 5 71 1.3400E+02 5.2000E+01 4.5000E+00 1.5000E-01 30639 5 72 1.3400E+02 5.3000E+01 5.8900E+00 1.6000E-01 4.0000E+0030639 5 73 1.3500E+02 5.3000E+01 5.2900E+00 1.1000E-01 30639 5 74 1.3500E+02 5.4000E+01 5.5800E+00 1.5000E-01 4.0000E+0030639 5 75 1.3700E+02 5.5000E+01 5.2100E+00 3.6000E-01 30639 5 76 1.3800E+02 5.4000E+01 4.2600E+00 4.4000E-01 30639 5 77 1.3800E+02 5.5000E+01 0.0000E+00 4.5300E+00 2.2000E-01 4.0000E+0030639 5 78 1.3900E+02 5.6000E+01 5.1300E+00 2.5000E-01 30639 5 79 1.4000E+02 5.6000E+01 4.6200E+00 7.0000E-02 30639 5 80 1.4000E+02 5.7000E+01 4.6300E+00 7.0000E-02 4.0000E+0030639 5 81 1.4100E+02 5.8000E+01 4.3800E+00 1.4000E-01 30639 5 82 1.4200E+02 5.7000E+01 4.1900E+00 1.4000E-01 30639 5 83 1.4300E+02 5.8000E+01 3.8500E+00 9.0000E-02 30639 5 84 1.4400E+02 5.8000E+01 3.3900E+00 2.2000E-01 30639 5 85 1.4600E+02 5.8000E+01 1.9190E+00 2.3400E-01 30639 5 86 1.4700E+02 6.0000E+01 2.3000E+00 1.0000E-01 30639 5 87 1.4900E+02 6.0000E+01 1.2900E+00 1.3700E-01 30639 5 88 ENDDATA 49 30639 5 89 ENDSUBENT 6 30639 599999 SUBENT 30639006 840912 30639 6 1 BIB 6 28 30639 6 2 REACTION (92-U-238(N,F)MASS,CHN,FY) 30639 6 3 METHOD CHAIN YIELDS ARE DEDUCED USING CHARGE DISTRIBUTION DATA30639 6 4 AND BRANCHING RATIOS FOR THE FORMATION OF THE MEASURED 30639 6 5 NUCLIDES FROM BETA DECAY OF THEIR PRECURSORS (BOTH 30639 6 6 TAKEN FROM M.E.MEEK AND B.F.RIDER,NEDO-12154-1,1974). 30639 6 7 COMPILERS NOTE = FOR THOSE 3 CASES WHERE THE CHAIN 30639 6 8 YIELD WAS DEDUCED USING (ONLY) BRANCHING RATIOS (SEE 30639 6 9 'MISC'-COLUMN AND 'FLAG'),THE DATA GIVEN BY MEEK AND 30639 6 10 RIDER INDICATE THAT DIRECT YIELDS OF THE NUCLIDES 30639 6 11 MEASURED OR THEIR ISOMERS CAN BE NEGLECTED WITHIN THE 30639 6 12 ERROR LIMITS OF THE EXPERIMENT. 30639 6 13 MISC-COL (MISC) DECAY BRANCHING RATIO USED (SEE 'METHOD') 30639 6 14 ERR-ANALYS THE ERRORS ARE ONE STANDARD DEVIATION AND (RELATIVE) 30639 6 15 THE SAME AS THOSE OF THE CUMULATIVE YIELDS FROM WHICH 30639 6 16 THE DATA WERE DERIVED.FOR THE TOTAL ERROR OF ABSOLUTE 30639 6 17 YIELDS A 3 PERCENT SYSTEMATIC UNCERTAINTY IN THE 30639 6 18 NEUTRON FLUX DETERMINATION HAS TO BE ADDED. 30639 6 19 COMPILERS NOTE = UNCERTAINTIES IN THE BRANCHING RATIOS 30639 6 20 AND CHARGE DISTRIBUTION DATA USED FOR CALCULATING CHAIN30639 6 21 YIELDS FROM MEASURED YIELDS ARE NOT TAKEN INTO ACCOUNT.30639 6 22 THE UNCERTAINTY CONTRIBUTION FROM CHARGE DISTRIBUTION 30639 6 23 DATA IS SIGNIFICANT ONLY FOR MASSES 132 AND 138. 30639 6 24 FLAG FLAGS ARE ONLY GIVEN FOR CHAIN YIELD VALUES DIFFERING 30639 6 25 FROM THE CUMULATIVE YIELDS FROM WHICH THEY WERE DEDUCED30639 6 26 (1.) DEDUCED USING BRANCHING RATIO (VALUE UNDER 'MISC')30639 6 27 (2.) DEDUCED USING CHARGE DISTRIBUTION DATA 30639 6 28 STATUS (DEP,30639005)AS THE WEIGHTED AVERAGE OF 30639 6 29 MEASURED CUMULATIVE YIELDS. 30639 6 30 ENDBIB 28 30639 6 31 COMMON 2 3 30639 6 32 EN-MIN EN-MAX 30639 6 33 MEV MEV 30639 6 34 1.4400E+01 1.4520E+01 30639 6 35 ENDCOMMON 2 3 30639 6 36 DATA 5 37 30639 6 37 MASS DATA DATA-ERR FLAG MISC 30639 6 38 NO-DIM PC/FIS PC/FIS NO-DIM NO-DIM 30639 6 39 8.3000E+01 7.2200E-01 1.4400E-01 1.0000E+00 3.6000E-01 30639 6 40 8.5000E+01 1.0230E+00 4.6000E-02 30639 6 41 8.7000E+01 1.8910E+00 8.3000E-02 30639 6 42 8.8000E+01 1.8290E+00 7.0000E-02 2.0000E+00 30639 6 43 8.9000E+01 2.8300E+00 1.4000E-01 2.0000E+00 30639 6 44 9.1000E+01 3.9800E+00 1.6000E-01 30639 6 45 9.2000E+01 3.7800E+00 1.0000E-01 30639 6 46 9.3000E+01 4.1000E+00 4.0000E-01 30639 6 47 9.5000E+01 4.6400E+00 9.0000E-02 30639 6 48 9.7000E+01 5.1200E+00 9.0000E-02 30639 6 49 9.9000E+01 5.7600E+00 1.2000E-01 30639 6 50 1.0100E+02 5.7600E+00 2.2000E-01 30639 6 51 1.0300E+02 4.5300E+00 1.2000E-01 30639 6 52 1.0400E+02 3.5900E+00 1.5000E-01 30639 6 53 1.0500E+02 3.1200E+00 8.0000E-02 30639 6 54 1.0600E+02 2.5400E+00 1.5000E-01 30639 6 55 1.1200E+02 1.0770E+00 5.2000E-02 30639 6 56 1.1500E+02 9.7500E-01 5.5000E-02 1.0000E+00 8.6500E-01 30639 6 57 1.2500E+02 1.2050E+00 7.3000E-02 30639 6 58 1.2700E+02 1.4310E+00 3.8000E-02 2.0000E+00 30639 6 59 1.2900E+02 3.1700E+00 3.1000E-01 1.0000E+00 1.6600E-01 30639 6 60 1.3100E+02 4.0400E+00 8.0000E-02 30639 6 61 1.3200E+02 4.8200E+00 6.0000E-02 2.0000E+00 30639 6 62 1.3300E+02 5.8000E+00 1.2000E-01 2.0000E+00 30639 6 63 1.3400E+02 5.9500E+00 1.6000E-01 2.0000E+00 30639 6 64 1.3500E+02 5.5800E+00 1.5000E-01 30639 6 65 1.3700E+02 5.2100E+00 3.6000E-01 30639 6 66 1.3800E+02 4.6100E+00 2.2000E-01 2.0000E+00 30639 6 67 1.3900E+02 5.1300E+00 2.5000E-01 30639 6 68 1.4000E+02 4.6300E+00 7.0000E-02 30639 6 69 1.4100E+02 4.3800E+00 1.4000E-01 30639 6 70 1.4200E+02 4.1900E+00 1.4000E-01 30639 6 71 1.4300E+02 3.8500E+00 9.0000E-02 30639 6 72 1.4400E+02 3.3900E+00 2.2000E-01 30639 6 73 1.4600E+02 1.9250E+00 2.3500E-01 2.0000E+00 30639 6 74 1.4700E+02 2.3000E+00 1.0000E-01 30639 6 75 1.4900E+02 1.2900E+00 1.3700E-01 30639 6 76 ENDDATA 39 30639 6 77 ENDSUBENT 5 30639 699999 SUBENT 30639007 841217 30639 7 1 BIB 13 32 30639 7 2 EXP-YEAR (69) FIRST EXPERIMENT 30639 7 3 REACTION (92-U-238(N,F)ELEM/MASS,IND,FY) LONG LIVED PRODUCTS 30639 7 4 INC-SOURCE NEUTRON FLUX=(7.80+-0.36)*10**6 N/(S*CM**2) RANDOM 30639 7 5 ERROR,OR +-3 PERCENT SYSTEMATIC ERROR 30639 7 6 IRRADIATION TIME=29.25 HOURS 30639 7 7 NUMBER OF FISSION EVENTS = 5.41*10**9 30639 7 8 SAMPLE 2640 GRAMS,THICKNESS=1.47 MM OR 921.4 MG/CM**2, 30639 7 9 DIAMETER=19.1 MM. 30639 7 10 DETECTOR (GELI).27 CCM, 4000 CHANNEL PULSE HEIGHT ANALYSER, 30639 7 11 RESOLUTION AT 662 KEV = 7.3 KEV. 30639 7 12 ANALYSIS (DECAY).DEDUCED FROM MEASURED GAMMA-SPECTRA OF THE 30639 7 13 NUCLIDE LISTED AND ITS PARENT. 30639 7 14 MONITOR (13-AL-27(N,A)11-NA-24,,SIG) MEASURED WITH GE(LI) DET. 30639 7 15 MONIT-REF (,H.VONACH+,J,ZP,273,155,70) 30639 7 16 DECAY-DATA FOR CALCULATION OF THE INDEPENDENT YIELD OF THE PRODUCT30639 7 17 LISTED THE HALF-LIFE OF ITS PRECURSOR (Z-1) IS ALSO 30639 7 18 USED. 30639 7 19 ((1.)53-I-135,6.585HR) 30639 7 20 ((1.)54-XE-135-G,9.17HR,DG,249.7,0.903) INCL. XE-135M 30639 7 21 ((2.)56-BA-140,12.79D) 30639 7 22 ((2.)57-LA-140,40.23HR,DG,487.0,0.46) 30639 7 23 ASSUMED (ASSUM,92-U-238(N,F),,SIG)M.G.SOWERBY+,AERE-R-7273,197330639 7 24 ERR-ANALYS ALL ERRORS QUOTED ARE ONE STANDARD DEVIATION. THEY 30639 7 25 INCLUDE CONTRIBUTIONS FROM PEAK AREA AND DECAY CURVE 30639 7 26 ANALYSIS,GAMMA-RAY INTENSITIES,DETECTOR EFFICIENCY 30639 7 27 AND RANDOM ERROR OF THE NEUTRON FLUX.NOT INCLUDED IS 30639 7 28 THE SYSTEMATIC 3 PERCENT UNCERTAINTY IN THE NEUTRON 30639 7 29 FLUX DETERMINATION,WHICH SHOULD BE ADDED WHEN 30639 7 30 CONSIDERING ABSOLUTE FISSION YIELDS. 30639 7 31 FLAG (1.) YIELD FOR BOTH ISOMERS.THE HALF-LIFE OF THE 30639 7 32 METASTABLE STATE IS NEGLECTED. 30639 7 33 STATUS (DEP,30639002) THE SAME RAW DATA ARE USED 30639 7 34 ENDBIB 32 30639 7 35 COMMON 5 3 30639 7 36 EN EN-ERR MONIT MONIT-ERR ASSUM 30639 7 37 MEV MEV MB MB MB 30639 7 38 1.4400E+01 1.9000E-01 1.1760E+02 5.0000E-01 1.1708E+03 30639 7 39 ENDCOMMON 5 3 30639 7 40 DATA 6 2 30639 7 41 MASS ELEMENT DATA DATA-ERR DECAY-FLAG FLAG 30639 7 42 NO-DIM NO-DIM PC/FIS PC/FIS NO-DIM NO-DIM 30639 7 43 1.3500E+02 5.4000E+01 2.9900E-01 1.0600E-01 1.0000E+00 1.0000E+0030639 7 44 1.4000E+02 5.7000E+01 4.6000E-02 5.0000E-02 2.0000E+00 30639 7 45 ENDDATA 4 30639 7 46 ENDSUBENT 6 30639 799999 SUBENT 30639008 850411 30639 8 1 BIB 13 52 30639 8 2 EXP-YEAR (71) SECOND EXPERIMENT,2 SAMPLES 30639 8 3 REACTION (92-U-238(N,F)ELEM/MASS,IND,FY) SHORT LIVED PRODUCTS 30639 8 4 INC-SOURCE NEUTRON FLUX=(2.10+-0.05)*10**8 N/(S*CM**2) RANDOM 30639 8 5 ERROR,OR +-3 PERCENT SYSTEMATIC ERROR, 30639 8 6 IRRADIATION TIME=5 MIN FOR EACH SAMPLE 30639 8 7 NUMBER OF FISSION EVENTS=3.92*10**8 FOR EACH SAMPLE 30639 8 8 SAMPLE 2490.4 GRAMS,THICKNESS=1.47 MM OR 921.4 MG/CM**2, 30639 8 9 DIAMETER=18.6 MM (BOTH SAMPLES) 30639 8 10 DETECTOR (GELI).20 CCM, 4000 CHANNEL PULSE HEIGHT ANALYSER, 30639 8 11 RESOLUTION AT 662 KEV = 4.63 KEV. 30639 8 12 ANALYSIS (DECAY).DEDUCED FROM MEASURED GAMMA-SPECTRA OF THE 30639 8 13 NUCLIDE LISTED AND ITS PARENT. 30639 8 14 MONITOR (29-CU-63(N,2N)29-CU-62,,SIG)USING 4-PI BETA COUNTING 30639 8 15 MONIT-REF (,Y.KANDA+,C,68WASH,1,193,68) 30639 8 16 DECAY-DATA FOR CALCULATION OF THE INDEPENDENT YIELD OF THE PRODUCT30639 8 17 LISTED THE HALF-LIFE OF ITS PRECURSOR (Z-1) IS ALSO 30639 8 18 USED. IF THE SUM OF YIELDS FOR BOTH ISOMERS IS GIVEN, 30639 8 19 A DECAY FLAG FOR THE SHORT LIVED METASTABLE STATE 30639 8 20 (GENERALLY NEGLECTED) IS NOT INCLUDED. 30639 8 21 ((1.)42-MO-101,14.6MIN) FOR DAUGHTER TC-101 30639 8 22 ((1.)43-TC-101,14.MIN,DG,306.8,0.875) 30639 8 23 ((2.)51-SB-131,23.0MIN) 30639 8 24 ((2.)52-TE-131-G,25.0MIN,DG,149.8,0.677) 30639 8 25 ((3.)51-SB-131,23.0MIN) 30639 8 26 ((3.)52-TE-131-G,25.0MIN,DG,149.8,0.677) 30639 8 27 ((3.)52-TE-131-M,30.HR,DG,149.8,0.364) 30639 8 28 ((4.)52-TE-134,42.MIN) FOR DAUGHTER I-134 30639 8 29 ((4.)53-I-134-G,52.6MIN,DG,847.0,0.954)INCLUDES I-134M 30639 8 30 ((5.)52-TE-134,42.MIN) FOR DAUGHTER I-134 30639 8 31 ((5.)53-I-134-G,52.6MIN,DG,884.1,0.653)INCLUDES I-134M 30639 8 32 ((6.)53-I-135,6.585HR) FOR DAUGHTER XE-135 30639 8 33 ((6.)54-XE-135-G,9.17HR,DG,249.7,0.903) INCL. XE-135M 30639 8 34 ((7.)54-XE-138,14.2MIN) FOR DAUGHTER CS-138-G 30639 8 35 ((7.)55-CS-138-G,32.2MIN,DG,1435.7,0.750) 30639 8 36 ASSUMED (ASSUM,92-U-238(N,F),,SIG)M.G.SOWERBY+,AERE-R-7273,197330639 8 37 ERR-ANALYS ALL ERRORS QUOTED ARE ONE STANDARD DEVIATION. THEY 30639 8 38 INCLUDE CONTRIBUTIONS FROM PEAK AREA AND DECAY CURVE 30639 8 39 ANALYSIS,GAMMA-RAY INTENSITIES,DETECTOR EFFICIENCY 30639 8 40 AND RANDOM ERROR OF THE NEUTRON FLUX.NOT INCLUDED IS 30639 8 41 THE SYSTEMATIC 3 PERCENT UNCERTAINTY IN THE NEUTRON 30639 8 42 FLUX DETERMINATION,WHICH SHOULD BE ADDED WHEN 30639 8 43 CONSIDERING ABSOLUTE FISSION YIELDS. 30639 8 44 FLAG (1.) DECAY BRANCHING RATIOS ARE TAKEN FROM H.E.MEEK AND30639 8 45 B.F.RIDER,NEDO-12154-1,1974.TE-131M CONTRIBUTES 30639 8 46 ONLY LITTLE TO THIS YIELD VALUE AND ITS DECAY-FLAG30639 8 47 (48.) IS NOT INCLUDED IN THIS LINE. 30639 8 48 (2.) SUM YIELD FOR BOTH ISOMERS. 30639 8 49 DECAY BRANCHING RATIOS ARE TAKEN FROM MEEK AND 30639 8 50 RIDER (SEE FLAG 1.). 30639 8 51 (3.) SUM YIELD FOR BOTH ISOMERS,DEDUCED FROM GROUND 30639 8 52 STATE DECAY. 30639 8 53 STATUS (DEP,30639003) THE SAME RAW DATA ARE USED 30639 8 54 ENDBIB 52 30639 8 55 COMMON 5 3 30639 8 56 EN EN-ERR MONIT MONIT-ERR ASSUM 30639 8 57 MEV MEV MB MB MB 30639 8 58 1.4400E+01 1.9000E-01 4.9700E+02 1.3000E+01 1.1708E+03 30639 8 59 ENDCOMMON 5 3 30639 8 60 DATA 7 7 30639 8 61 MASS ELEMENT ISOMER DATA DATA-ERR DECAY-FLAG 30639 8 62 FLAG 30639 8 63 NO-DIM NO-DIM NO-DIM PC/FIS PC/FIS NO-DIM 30639 8 64 NO-DIM 30639 8 65 1.0100E+02 4.3000E+01 2.6800E-01 5.7700E-01 1.0000E+0030639 8 66 30639 8 67 1.3100E+02 5.2000E+01 0.0000E+00 1.3770E+00 2.0800E-01 2.0000E+0030639 8 68 1.0000E+00 30639 8 69 1.3100E+02 5.2000E+01 1.5580E+00 2.1100E-01 3.0000E+0030639 8 70 2.0000E+00 30639 8 71 1.3400E+02 5.3000E+01 1.4290E+00 2.1300E-01 4.0000E+0030639 8 72 3.0000E+00 30639 8 73 1.3400E+02 5.3000E+01 1.5350E+00 1.7030E+00 5.0000E+0030639 8 74 3.0000E+00 30639 8 75 1.3500E+02 5.4000E+01 3.1900E-01 7.8000E-02 6.0000E+0030639 8 76 3.0000E+00 30639 8 77 1.3800E+02 5.5000E+01 0.0000E+00 2.4600E-01 5.8300E-01 7.0000E+0030639 8 78 30639 8 79 ENDDATA 18 30639 8 80 ENDSUBENT 7 30639 899999 SUBENT 30639009 840912 30639 9 1 BIB 4 21 30639 9 2 REACTION (92-U-238(N,F)ELEM/MASS,IND,FY) COMBINED RESULTS 30639 9 3 ERR-ANALYS THE ERRORS ARE ONE STANDARD DEVIATION CALCULATED FROM 30639 9 4 THE ERRORS OF INDIVIDUAL MEASUREMENTS AS COMPILED IN 30639 9 5 THE PRECEDING SUBENTRIES.FOR THE TOTAL ERROR OF 30639 9 6 ABSOLUTE YIELDS A 3 PERCENT SYSTEMATIC UNCERTAINTY IN 30639 9 7 THE NEUTRON FLUX DETERMINATION HAS TO BE ADDED. 30639 9 8 FLAG (1.)THE AUTHORS STATE IN A FOOTNOTE TO TABLE III,THAT 30639 9 9 THE TE-131M INDEPENDENT YIELD WAS DEDUCED FROM THE 30639 9 10 CUMULATIVE YIELDS OF SB-131 AND TE-131M,USING DECAY30639 9 11 BRANCHING RATIOS FROM M.E.MEEK AND B.F.RIDER, 30639 9 12 NEDO-12154-1,1974. 30639 9 13 COMPILERS COMMENT = SINCE THE INDEPENDENT YIELDS OF 30639 9 14 TE-131M AND TE-131G ADD UP EXACTLY TO THE COMBINED 30639 9 15 YIELD GIVEN FOR BOTH ISOMERS (AS IN SUBENTRY 8),IT 30639 9 16 SEEMS THAT ALL INDEPENDENT AND CUMULATIVE YIELD DATA 30639 9 17 FOR MASS=131 (EXCEPT I-131) HAVE BEEN OBTAINED IN A 30639 9 18 COMBINED DECAY CURVE ANALYSIS FROM THE 2ND EXPERIMENT 30639 9 19 (2.) YIELD FOR BOTH ISOMERS.FOR TE-131 SEE ALSO FLAG 1.30639 9 20 STATUS (DEP,30639007) AND 30639 9 21 (DEP,30639008) AS WEIGHTED AVERAGE OF INDIVIDUAL 30639 9 22 RESULTS OF BOTH EXPERIMENTS. 30639 9 23 ENDBIB 21 30639 9 24 COMMON 1 3 30639 9 25 EN 30639 9 26 MEV 30639 9 27 1.4400E+01 30639 9 28 ENDCOMMON 1 3 30639 9 29 DATA 6 8 30639 9 30 MASS ELEMENT ISOMER DATA DATA-ERR FLAG 30639 9 31 NO-DIM NO-DIM NO-DIM PC/FIS PC/FIS NO-DIM 30639 9 32 1.0100E+02 4.3000E+01 2.6800E-01 5.7700E-01 30639 9 33 1.3100E+02 5.2000E+01 1.0000E+00 1.8100E-01 3.6000E-02 1.0000E+0030639 9 34 1.3100E+02 5.2000E+01 0.0000E+00 1.3770E+00 2.0800E-01 1.0000E+0030639 9 35 1.3100E+02 5.2000E+01 1.5580E+00 2.1100E-01 2.0000E+0030639 9 36 1.3400E+02 5.3000E+01 1.4310E+00 2.1100E-01 2.0000E+0030639 9 37 1.3500E+02 5.4000E+01 3.1200E-01 6.3000E-02 2.0000E+0030639 9 38 1.3800E+02 5.5000E+01 0.0000E+00 2.4600E-01 5.8300E-01 30639 9 39 1.4000E+02 5.7000E+01 4.6000E-02 5.0000E-02 30639 9 40 ENDDATA 10 30639 9 41 ENDSUBENT 6 30639 999999 SUBENT 30639010 840912 30639 10 1 BIB 4 10 30639 10 2 REACTION ((92-U-238(N,F)ELEM/MASS,IND,FY)/ 30639 10 3 (92-U-238(N,F)MASS,CHN,FY))FRACTIONAL INDEPENDENT YIELD30639 10 4 ERR-ANALYS THE ERRORS ARE ONE STANDARD DEVIATION REPRESENTING THE 30639 10 5 COMBINED ERRORS OF INDEPENDENT AND CHAIN YIELDS. 30639 10 6 COMPILERS COMMENT = THE 3 PERCENT SYSTEMATIC ERROR OF 30639 10 7 THE NEUTRON FLUX CANCELS IN THE RATIO AND MUST NOT BE 30639 10 8 INCLUDED IN THE TOTAL ERROR. 30639 10 9 FLAG (1.) SUM YIELDS FOR BOTH ISOMERS 30639 10 10 STATUS (DEP,30639009) INDEPENDENT YIELDS, DIVIDED BY 30639 10 11 (DEP,30639006) TOTAL CHAIN YIELDS. 30639 10 12 ENDBIB 10 30639 10 13 COMMON 1 3 30639 10 14 EN 30639 10 15 MEV 30639 10 16 1.4400E+01 30639 10 17 ENDCOMMON 1 3 30639 10 18 DATA 6 6 30639 10 19 MASS ELEMENT ISOMER DATA DATA-ERR FLAG 30639 10 20 NO-DIM NO-DIM NO-DIM NO-DIM NO-DIM NO-DIM 30639 10 21 1.0100E+02 4.3000E+01 4.5000E-02 9.7000E-02 30639 10 22 1.3100E+02 5.2000E+01 3.8600E-01 5.3000E-02 1.0000E+0030639 10 23 1.3400E+02 5.3000E+01 2.4200E-01 3.7000E-02 1.0000E+0030639 10 24 1.3500E+02 5.4000E+01 5.6000E-02 1.2000E-02 1.0000E+0030639 10 25 1.3800E+02 5.5000E+01 0.0000E+00 5.4000E-02 1.2700E-01 30639 10 26 1.4000E+02 5.7000E+01 1.0000E-02 1.1000E-02 30639 10 27 ENDDATA 8 30639 10 28 ENDSUBENT 6 30639 1099999 ENDENTRY 10 3063999999999 ENTRY 30695 851210 30695 0 1 SUBENT 30695001 851210 30695 1 1 BIB 14 34 30695 1 2 INSTITUTE (3CPRIMP) 30695 1 3 REFERENCE (J,PHE,6,365,8205) IN CHINESE 30695 1 4 (S,LBL-1118,928,8008) ABSTRACT OF THE INT. CONF. ON 30695 1 5 NUCLEAR PHYSICS,BERKELEY,CALIF.,24-30 AUGUST 1980. 30695 1 6 PRELIMINARY RESULTS.SUPERSEDED. 30695 1 7 AUTHOR (LI WENXIN, SUN TONGYU, SUN XIUHUA, ZHANG TIANMEI, 30695 1 8 ZHENG MANJIAO, DONG TIANRONG, FU MING) 30695 1 9 TITLE CHARGE DISTRIBUTION IN THE FISSION OF TH-232 BY 14 MEV 30695 1 10 NEUTRONS 30695 1 11 FACILITY (CCW,3CPRIMP) NO DETAILS GIVEN 30695 1 12 INC-SOURCE (D-T) 30695 1 13 NEUTRON FLUX ABOUT (1-2)*E+11 NEUTRONS/4PI/SEC 30695 1 14 SAMPLE TH(NO3)4.6H2O,PURE THORIUM SAMPLE 30695 1 15 METHOD (CHSEP) 30695 1 16 FIRST, FISSION PRODUCTS WERE SEPARATED FROM THE 30695 1 17 IRRADIATED SAMPLES BY RADIOCHEMISTRY METHODS AND 30695 1 18 WEIGHED FOR THE DETERMINATION OF THE CHEMICAL YIELD. 30695 1 19 THEM FISSION PRODUCT GAMMA RAYS WERE MEASURED WITH 30695 1 20 CALIBRATED GE(LI) DETECTORS FOR DETERMINING 30695 1 21 INDEPENDENT FISSION YIELDS. 30695 1 22 DETECTOR (GELI) 80 CM3 AND 140 CM3, RESOLUTION 1.9 AND 2.4 KEV 30695 1 23 FWHM AT 1332 KEV RESPECTIVELY, TOGETHER WITH A 30695 1 24 MULTI-CHANNEL ANALYSER. THE DETECTOR EFFICIENCY WAS 30695 1 25 CALIBRATED USING WELL KNOWN GAMMA-RAY STANDARDS. 30695 1 26 PART-DET (G) 30695 1 27 CORRECTION MADE FOR THE LOSS OF PHOTOELECTRONS DUE TO RANDOM PULSE30695 1 28 PILE-UP, AND FOR PRECURSOR DECAY IN THE CASE OF AG-112,30695 1 29 I-132 AND I-134 INDEPENDENT YIELD DETERMINATION. 30695 1 30 ERR-ANALYS ERRORS GIVEN IN THE DATA TABLES ARE TOTAL EXPERIMENTAL 30695 1 31 ERRORS. THE ERRORS DUE TO THE ERRORS OF HALF LIFE, 30695 1 32 GAMMA INTENSITY, AND REFERENCE FISSION YIELD USED FOR 30695 1 33 FISSION YIELD CALCULATION WERE NOT INCLUDED 30695 1 34 STATUS DATA TAKEN FROM TABLE 1 OF THE FIRST PUBLICATION 30695 1 35 HISTORY (851030C) COMPILED BY LIANG QICHANG AND M. LAMMER 30695 1 36 ENDBIB 34 30695 1 37 NOCOMMON 0 0 30695 1 38 ENDSUBENT 0 30695 199999 SUBENT 30695002 851210 30695 2 1 BIB 4 5 30695 2 2 REACTION (90-TH-232(N,F)ELEM/MASS,IND,FY) 30695 2 3 MONITOR (90-TH-232(N,F)42-MO-99,CUM,FY) 30695 2 4 MONIT-REF (,D.L.SWINDLE+,J,JIN,33,651,71) 30695 2 5 COMMENT FOR FISSION PRODUCT LA-140, FISSION YIELD GIVEN IN THE30695 2 6 TABLE WAS THE UPPER LIMIT OF THE DATA OBTAINED 30695 2 7 ENDBIB 5 30695 2 8 COMMON 3 3 30695 2 9 EN EN-RSL MONIT 30695 2 10 MEV MEV PC/FIS 30695 2 11 1.4500E+01 4.0000E-01 2.0000E+00 30695 2 12 ENDCOMMON 3 3 30695 2 13 DATA 6 10 30695 2 14 ELEMENT MASS ISOMER HL DATA ERR-T 30695 2 15 NO-DIM NO-DIM NO-DIM MIN PC/FIS PC/FIS 30695 2 16 3.5000E+01 8.2000E+01 1.0000E-04 2.0000E-0530695 2 17 4.1000E+01 9.6000E+01 1.8000E-04 1.1000E-0430695 2 18 4.7000E+01 1.1200E+02 5.0000E-03 2.0000E-0330695 2 19 5.3000E+01 1.3000E+02 1.2000E-03 3.0000E-0430695 2 20 5.3000E+01 1.3200E+02 9.7000E-02 1.9000E-0230695 2 21 5.3000E+01 1.3400E+02 7.8000E-01 2.6000E-0130695 2 22 5.5000E+01 1.3400E+02 1.0000E+00 1.7400E+02 3.1000E-04 1.6000E-0430695 2 23 5.5000E+01 1.3500E+02 1.0000E+00 5.3000E+01 5.5000E-03 1.9000E-0330695 2 24 5.5000E+01 1.3600E+02 1.0000E-02 2.0000E-0330695 2 25 5.7000E+01 1.4000E+02 3.5000E-02 30695 2 26 ENDDATA 12 30695 2 27 ENDSUBENT 6 30695 299999 SUBENT 30695003 851210 30695 3 1 BIB 3 9 30695 3 2 REACTION (90-TH-232(N,F)ELEM/MASS,IND,FY)/ 30695 3 3 (90-TH-232(N,F)MASS,CHN,FY) 30695 3 4 COMMENT USING THE SMOOTH MASS DISTRIBUTION CURVE FROM 30695 3 5 ANL-6515(1977), THE INDEPENDENT YIELDS WERE 30695 3 6 CONVERTED INTO FRACTIONAL INDEPENDENT YIELDS. 30695 3 7 FOR FISSION PRODUCT LA-140, THE FRACTIONAL INDEPENDENT 30695 3 8 YIELD GIVEN IN THE TABLE IS THE UPPER LIMIT OF THE 30695 3 9 MEASURED DATA. 30695 3 10 STATUS (DEP,30695002) INDEPENDENT YIELDS GIVEN IN THE TABLE 30695 3 11 ENDBIB 9 30695 3 12 COMMON 2 3 30695 3 13 EN EN-RSL 30695 3 14 MEV MEV 30695 3 15 1.4500E+01 4.0000E-01 30695 3 16 ENDCOMMON 2 3 30695 3 17 DATA 6 10 30695 3 18 ELEMENT MASS ISOMER HL DATA ERR-T 30695 3 19 NO-DIM NO-DIM NO-DIM MIN NO-DIM NO-DIM 30695 3 20 3.5000E+01 8.2000E+01 7.5000E-05 1.5000E-0530695 3 21 4.1000E+01 9.6000E+01 3.3000E-05 2.0000E-0530695 3 22 4.7000E+01 1.1200E+02 3.4000E-03 1.4000E-0330695 3 23 5.3000E+01 1.3000E+02 8.3000E-04 2.1000E-0430695 3 24 5.3000E+01 1.3200E+02 3.6000E-02 7.0000E-0330695 3 25 5.3000E+01 1.3400E+02 1.6000E-01 5.0000E-0230695 3 26 5.5000E+01 1.3400E+02 1.0000E+00 1.7400E+02 6.7000E-05 3.4000E-0530695 3 27 5.5000E+01 1.3500E+02 1.0000E+00 5.3000E+01 1.0000E-03 3.0000E-0430695 3 28 5.5000E+01 1.3600E+02 1.9000E-03 4.0000E-0430695 3 29 5.7000E+01 1.4000E+02 6.4000E-03 30695 3 30 ENDDATA 12 30695 3 31 ENDSUBENT 6 30695 399999 ENDENTRY 3 3069599999999 ENTRY 30768 871214 30768 0 1 SUBENT 30768001 871214 30768 1 1 BIB 17 74 30768 1 2 INSTITUTE (3INDBHU) 30768 1 3 REFERENCE (J,NIM/B,24/25,501,8704) 30768 1 4 AUTHOR (S.RAM,N.L.SINGH,S.K.BOSE,J.R.RAO) 30768 1 5 TITLE ABSOLUTE YIELDS OF SOME FISSION PRODUCTS IN THE 14 MEV 30768 1 6 NEUTRON INDUCED FISSION OF U-238 30768 1 7 FACILITY (VDG) 30768 1 8 INC-SOURCE (D-T) FLUX=2.26*10E+9 N/CM2/S 30768 1 9 SAMPLE ABOUT 1 MG OF SOLID URANYL NITRATE 30768 1 10 METHOD 'TRACK-ETCH-CUM-GAMMA-RAY SPECTROMETRY' 30768 1 11 THE SAMPLE WAS IRRADIATED TOGETHER WITH A MONITOR TUBE 30768 1 12 ON EITHER SIDE IN NEUTRON BEAM DIRECTION. 30768 1 13 FISSION TRACKS WERE COUNTED WITH AN OPTICAL MICROSCOPE.30768 1 14 THE TRACK DENSITY WAS DETERMINED 30768 1 15 DIRECT GAMMA-RAY SPECTROSCOPY OF UNSEPARATED FISSION 30768 1 16 PRODUCTS BY MEASURING THE SOLID SAMPLE. 30768 1 17 DETECTOR (TRD) LEXAN PLASTIC FISSION TRACK DETECTOR 30768 1 18 THE EFFICIENCY FOR TRACK REGISTRATION IN SOLUTION HAS30768 1 19 BEEN DETERMINED BY COMPARISON WITH ANOTHER LEXAN 30768 1 20 DETECTOR ON WHICH A KNOWN AMOUNT OF SOLUTION WAS 30768 1 21 EVAPORATED. 30768 1 22 (HPGE).,PRECALIBRATED,RESOLUTION: 2 KEV AT 1.33 MEV, 30768 1 23 COUPLED TO A MULTICHANNEL ANALYSER. 30768 1 24 THE DETECTOR EFFICIENCY FOR THE MEASURED FISSION 30768 1 25 PRODUCT GAMMA-RAYS IS GIVEN IN TABLE 1 OF NUCL.INSTR.30768 1 26 METH.PHYS.RES. B24/25(1987)501. 30768 1 27 ANALYSIS THE TOTAL NUMBER OF FISSIONS WAS DERIVED FROM THE 30768 1 28 FISSION TRACK DENSITY TAKING INTO ACCOUNT: 30768 1 29 - WEIGHT OF THE FISSILE MATERIAL 30768 1 30 - EFFICIENCY FOR TRACK REGISTRATION IN SOLUTION 30768 1 31 - CONCENTRATION OF TARGET MATERIAL IN SOLUTION 30768 1 32 DETAILS ARE GIVEN IN THE MAIN PUBLICATION 30768 1 33 FISSION YIELDS ARE DERIVED FROM MEASURED ACTIVITIES 30768 1 34 AND TOTAL NUMBER OF FISSIONS USING A STANDARD FORMULA30768 1 35 CONTAINING FACTORS FOR DECAY DURING IRRADIATION, 30768 1 36 COOLING AND DATA ACCUMULATION. 30768 1 37 COMPILERS COMMENT: THE FORMULA DOES NOT ACCOUNT FOR 30768 1 38 ANY PRECURSORS IN DECAY. 30768 1 39 MONITOR ABSOLUTE MEASUREMENT OF THE NUMBER OF FISSIONS:AQUEOUS 30768 1 40 SOLUTION OF URANYL NITRATE IN A THIN GLASS TUBE 30768 1 41 CONTAINING THE FISSION DETECTOR (LEXAN). 30768 1 42 DECAY-DATA ((1.)42-MO-99,66.02HR,DG,739.4,0.126) 30768 1 43 ((2.)48-CD-115,53.38HR,DG,527.7,0.339) 30768 1 44 ((3.)48-CD-117-M,3.31HR,DG,564.4,0.152) 30768 1 45 ((4.)51-SB-126,12.4D,DG,666.3,0.997) 30768 1 46 ((5.)51-SB-128-G,9.1HR,DG,314.1,0.610) 30768 1 47 ((6.)52-TE-131-M,30.0HR,DG,773.7,0.380) 30768 1 48 ((7.)56-BA-140,12.789D,DG,537.2,0.236) 30768 1 49 ((8.)58-CE-141,32.55D,DG,145.0,0.484) 30768 1 50 ((9.)61-PM-151,28.4HR,DG,167.7,0.077) 30768 1 51 ((10.)63-EU-157,15.15HR,DG,410.6,0.190) 30768 1 52 DATA TAKEN FROM C.M.LEDERER,V.S.SHIRLEY,TABLE OF 30768 1 53 ISOTOPES,SEVENTH EDITION,1978. 30768 1 54 ERR-ANALYS NO INFORMATION 30768 1 55 COMMENT BY COMPILER: THE FOLLOWING INFORMATION PERTINENT TO 30768 1 56 EVALUATORS IS MISSING OR INSUFFICIENT IN THE PAPER: 30768 1 57 - EXACT VALUE OF THE NEUTRON ENERGY 30768 1 58 - DURATION OF IRRADIATION,COOLING AND MEASUREMENTS. 30768 1 59 - ANALYSIS OF GAMMA-SPECTRA: INTERFERING PEAKS, 30768 1 60 UNCERTAINTIES INVOLVED. 30768 1 61 - GENETIC PARENT-DAUGHTER RELATIONSHIPS; DETAILS ON THE30768 1 62 WAY YIELDS WERE OBTAINED. 30768 1 63 - ERROR ANALYSIS: TYPES AND NUMERICAL VALUES OF 30768 1 64 DIFFERENT ERROR CONTRIBUTIONS INVOLVED/CONSIDERED. 30768 1 65 CRITIQUE IN THE FOLLOWING CASES IT IS UNCLEAR WHAT TYPE OF YIELD30768 1 66 THE VALUES REPRESENT (OR THE VALUES ARE DOUBTFUL): 30768 1 67 1. SB-126: SHIELDED BY 10E+5 YEAR SN-126 30768 1 68 2. SB-128 HAS A METASTABLE STATE WHICH IS FED BY BETA 30768 1 69 DECAY OF SN-128 BUT DECAYS ONLY TO 3.6 % TO SB-128G.30768 1 70 3. TE-131M IS FED ONLY IN 6.8 % OF SB-131 BETA DECAYS. 30768 1 71 THE YIELD VALUE GIVEN SEEMS TO BE TOO HIGH FOR THE 30768 1 72 CUMULATIVE YIELD OF THE METASTABLE STATE. 30768 1 73 THESE POINTS NEED CLARIFICATION. 30768 1 74 STATUS (TABLE) DATA TAKEN FROM TABLE 1 OF FIRST REFERENCE 30768 1 75 HISTORY (871204C) ML 30768 1 76 ENDBIB 74 30768 1 77 COMMON 1 3 30768 1 78 EN 30768 1 79 MEV 30768 1 80 14. 30768 1 81 ENDCOMMON 1 3 30768 1 82 ENDSUBENT 1 30768 199999 SUBENT 30768002 871214 30768 2 1 BIB 2 2 30768 2 2 REACTION (92-U-238(N,F)ELEM/MASS,CUM,FY) 30768 2 3 FLAG (1.) SEE 'CRITIQUE' 30768 2 4 ENDBIB 2 30768 2 5 NOCOMMON 0 0 30768 2 6 DATA 7 10 30768 2 7 ELEMENT MASS ISOMER DATA DATA-ERR DECAY-FLAG 30768 2 8 FLAG 30768 2 9 NO-DIM NO-DIM NO-DIM PC/FIS PC/FIS NO-DIM 30768 2 10 NO-DIM 30768 2 11 42. 99. 5.84 0.29 1. 30768 2 12 30768 2 13 48. 115. 0. 0.57 0.02 2. 30768 2 14 30768 2 15 48. 117. 1. 0.15 0.01 3. 30768 2 16 30768 2 17 51. 126. 0. 0.25 0.01 4. 30768 2 18 1. 30768 2 19 51. 128. 0. 0.21 0.01 5. 30768 2 20 1. 30768 2 21 52. 131. 1. 4.10 0.20 6. 30768 2 22 1. 30768 2 23 56. 140. 4.34 0.17 7. 30768 2 24 30768 2 25 58. 141. 4.46 0.17 8. 30768 2 26 30768 2 27 61. 151. 0.89 0.04 9. 30768 2 28 30768 2 29 63. 157. 0.11 0.01 10. 30768 2 30 30768 2 31 ENDDATA 24 30768 2 32 ENDSUBENT 7 30768 299999 ENDENTRY 2 3076899999999 ENTRY 30785 950627 30785 0 1 SUBENT 30785001 950627 30785 1 1 BIB 11 32 30785 1 2 INSTITUTE (3CPRIMP) 30785 1 3 REFERENCE (J,PHE,11,376,8705) IN CHINESE 30785 1 4 (C,86BEIJIN,47,8609) 30785 1 5 AUTHOR (LI WENXIN,SUN TONGYU,SUN XIUHUA,FU MING,DONG TIANRONG,30785 1 6 ZHENG MANJIAO) 30785 1 7 TITLE CHARGE DISTRIBUTION IN THE 14.7 MEV NEUTRON INDUCED 30785 1 8 FISSION OF TH-232: INDEPENDENT YIELDS OF ISOTOPES OF 30785 1 9 RH, AG, IN AND SB. 30785 1 10 FACILITY (CCW) 30785 1 11 INC-SOURCE (D-T)., 400KV GENERATOR 30785 1 12 NEUTRON FLUX = 2*10E11 N/CM2/SEC 30785 1 13 SAMPLE ANALYTICALLY PURE TH(NO3)4*6H2O 30785 1 14 METHOD (RCHEM,GSPEC) 30785 1 15 THE SAMPLE WAS DISSOLVED IN HCL AND HNO3; THE FISSION 30785 1 16 PRODUCTS RU, RH, PD, CD, IN, SB, TE, AND MO (MONITOR 30785 1 17 PRODUCT), WERE SEPARATED USING STANDARD PROCEDURES: 30785 1 18 SEE, E.G., HE HUAXUE YU FANGSHE HUAXUE (=J.NUCLEAR AND 30785 1 19 RADIOCHEM.) ,VOL.2 (NO.1),P.9. 30785 1 20 THE SEPARATED PRODUCTS WERE MOUNTED FOR MEASUREMENT. 30785 1 21 DETECTOR (GELI) 2 GE(LI)-DETECTORS, VOLUMES: 80 AND 140 CCM; 30785 1 22 RESOLUTION AT 1332 KEV: 1.9 AND 2.4 KEV RESPECTIVELY. 30785 1 23 ERR-ANALYS ERROR OF EFFICIENCY CALIBRATION: ABOUT 5 %. 30785 1 24 THE ERRORS GIVEN ARE 1 STANDARD DEVIATION, CALCULATED 30785 1 25 AS THE WEIGHTED AVERAGES OF 3-6 DETERMINATIONS. 30785 1 26 THE ERROR OF THE MONITOR IS NOT INCLUDED. 30785 1 27 COMPILER'S (ML) COMMENT: 30785 1 28 IT IS NOT STATED WHETHER THE ERROR OF THE EFFICIENCY 30785 1 29 CALIBRATION IS INCLUDED 30785 1 30 NO OTHER INFORMATION IS GIVEN. 30785 1 31 HISTORY (891008C) DW/ML 30785 1 32 (930125A) HW.-CORRECTIONS MADE IN SUBENTS 003, 004.- 30785 1 33 (950517A) HW.-REFERENCE ADDED IN SUBENT 001.- 30785 1 34 ENDBIB 32 30785 1 35 COMMON 2 3 30785 1 36 EN EN-ERR 30785 1 37 MEV MEV 30785 1 38 14.7 0.3 30785 1 39 ENDCOMMON 2 3 30785 1 40 ENDSUBENT 2 30785 199999 SUBENT 30785002 891010 30785 2 1 BIB 6 25 30785 2 2 REACTION (90-TH-232(N,F)ELEM/MASS,CUM,FY) 30785 2 3 MONITOR (90-TH-232(N,F)42-MO-99,CUM,FY) VALUE FOR 14.0 MEV 30785 2 4 MONIT-REF (,D.L.SWINDLE,J,JIN,33,651,71) 30785 2 5 DECAY-DATA ((1.)44-RU-103,39.4D,DG,497.1,0.864) 30785 2 6 ((2.)44-RU-105,4.44HR) 30785 2 7 ((3.)44-RU-106,368.D) 30785 2 8 ((4.)47-AG-111-G,7.47D) 30785 2 9 ((5.)46-PD-112,21.05HR) 30785 2 10 ((6.)47-AG-113,5.37HR) ASSUMED BY COMPILER (ISOMER NOT 30785 2 11 GIVEN IN PAPER) 30785 2 12 ((7.)48-CD-115-G,53.5HR) 30785 2 13 ((8.)48-CD-117-G,2.40HR) 30785 2 14 ((9.)48-CD-117-M,3.40HR) 30785 2 15 ((10.)51-SB-125,2.77YR) 30785 2 16 ((11.)51-SB-127,3.85D) 30785 2 17 ((12.)51-SB-129,4.32HR) 30785 2 18 ((13.)52-TE-132,78.2HR) 30785 2 19 THE DECAY DATA WERE TAKEN FROM THE GAMMA-RAY CATALOG: 30785 2 20 U.REUS ET AL, REPORT GSI 79-2 (FEB.1979) 30785 2 21 THE DATA USED ARE NOT GIVEN IN THE PAPER. THEREFORE 30785 2 22 ONLY THE HALF LIVES GIVEN IN THE ABOVE REPORT ARE 30785 2 23 REPRODUCED HERE, BUT GAMMA-RAYS ARE OMITTED UNLESS 30785 2 24 THERE IS NO DOUBT AS TO WHICH ONE HAS BEEN USED. 30785 2 25 DECAY-MON (42-MO-99,66.0HR) SOURCE: SEE UNDER DECAY-DATA 30785 2 26 STATUS DATA TAKEN FROM TABLE 1 OF HIGH EN.NUCL.PHYS. 11 376 30785 2 27 ENDBIB 25 30785 2 28 COMMON 3 3 30785 2 29 MONIT MONIT-ERR EN-NRM 30785 2 30 PC/FIS PC/FIS MEV 30785 2 31 2.0 0.1 14.0 30785 2 32 ENDCOMMON 3 3 30785 2 33 DATA 6 13 30785 2 34 MASS ELEMENT ISOMER DATA DATA-ERR DECAY-FLAG 30785 2 35 NO-DIM NO-DIM NO-DIM PC/FIS PC/FIS NO-DIM 30785 2 36 103. 44. 0.82 0.09 1.00030785 2 37 105. 44. 1.13 0.12 2.00030785 2 38 106. 44. 1.18 0.15 3.00030785 2 39 111. 47. 0. 1.11 0.16 4.00030785 2 40 112. 46. 1.24 0.13 5.00030785 2 41 113. 47. 1.38 0.12 6.00030785 2 42 115. 48. 0. 1.23 0.10 7.00030785 2 43 117. 48. 0. 1.12 0.11 8.00030785 2 44 117. 48. 1. 0.25 0.03 9.00030785 2 45 125. 51. 0.68 0.07 10. 30785 2 46 127. 51. 1.22 0.10 11. 30785 2 47 129. 51. 1.20 0.12 12. 30785 2 48 132. 52. 2.30 0.21 13. 30785 2 49 ENDDATA 15 30785 2 50 ENDSUBENT 6 30785 299999 SUBENT 30785003 930430 30785 3 1 BIB 9 27 30785 3 2 REACTION (90-TH-232(N,F)ELEM/MASS,IND,FY) 30785 3 3 METHOD A SEPARATE IRRADIATION OF ABOUT 10 MIN WAS PERFORMED 30785 3 4 FOR THE DETERMINATION OF THE INDEPENDENT YIELDS OF 30785 3 5 AG-112 AND IN-115M. SEPARATION TIME FROM THEIR 30785 3 6 RESPECTIVE PARENTS: AG: <10 MIN, IN: ABOUT 20 MIN. 30785 3 7 MONITOR (90-TH-232(N,F)42-MO-99,CUM,FY) VALUE FOR 14.0 MEV 30785 3 8 MONIT-REF (,D.L.SWINDLE,J,JIN,33,651,71) 30785 3 9 DECAY-DATA ((1.)45-RH-106-M,2.2HR) 30785 3 10 ((2.)47-AG-112,3.12HR) SEE COMMENT BELOW 30785 3 11 ((3.)49-IN-115-M,4.49HR) 30785 3 12 ((4.)49-IN-116-M1,54.2MIN) 30785 3 13 ((5.)51-SB-124-G,60.2D) 30785 3 14 ((6.)51-SB-126-G,12.4D) 30785 3 15 ((7.)51-SB-128-G,9.01HR) 30785 3 16 THE HALF-LIVES ARE GIVEN IN TABLE 2 OF HIGH EN.NUCL. 30785 3 17 PHYS. 11 376. IT IS ASSUMED THAT THE GAMMA-RAY DATA 30785 3 18 WERE ALSO TAKEN FROM: U.REUS ET AL, GSI 79-2 (2/1979), 30785 3 19 BUT THEY ARE NOT REPRODUCED HERE. 30785 3 20 - COMMENT: TABLE 2 OF HIGH EN.NUCL.PHYS. 11 376 GIVES 30785 3 21 'AG-112M' BUT AG-112 DOES NOT HAVE A METASTABLE STATE30785 3 22 DECAY-MON (42-MO-99,66.0HR) SOURCE: SEE UNDER DECAY-DATA 30785 3 23 FLAG (1.) AN UPPER LIMIT ONLY IS GIVEN AS THE GAMMA-RAY 30785 3 24 ACTIVITY WAS TOO LOW. 30785 3 25 STATUS DATA TAKEN FROM TABLE 2 OF HIGH EN.NUCL.PHYS. 11 376 30785 3 26 HISTORY (900424A) VOF.-REACTION CODE CORRECTED.- 30785 3 27 (930125A) HW.-DECAY-DATA CORRECTED, BLANK RECORD 30785 3 28 REMOVED.- 30785 3 29 ENDBIB 27 30785 3 30 COMMON 3 3 30785 3 31 MONIT MONIT-ERR EN-NRM 30785 3 32 PC/FIS PC/FIS MEV 30785 3 33 2.0 0.1 14.0 30785 3 34 ENDCOMMON 3 3 30785 3 35 DATA 8 7 30785 3 36 ELEMENT MASS ISOMER DATA DATA-ERR DATA-MAX 30785 3 37 DECAY-FLAG FLAG 30785 3 38 NO-DIM NO-DIM NO-DIM PC/FIS PC/FIS PC/FIS 30785 3 39 NO-DIM NO-DIM 30785 3 40 45. 106. 1. 1.5E-04 0.7E-04 30785 3 41 1. 30785 3 42 47. 112. 6.2E-03 2.1E-03 30785 3 43 2. 30785 3 44 49. 115. 1. 1.E-0330785 3 45 3. 1. 30785 3 46 49. 116. 1. 8.3E-03 3.3E-03 30785 3 47 4. 30785 3 48 51. 124. 0. 1.2E-0330785 3 49 5. 1. 30785 3 50 51. 126. 0. 3.2E-02 0.6E-02 30785 3 51 6. 30785 3 52 51. 128. 0. 3.4E-01 0.2E-01 30785 3 53 7. 30785 3 54 ENDDATA 18 30785 3 55 ENDSUBENT 8 30785 399999 SUBENT 30785004 930430 30785 4 1 BIB 7 35 30785 4 2 REACTION ((90-TH-232(N,F)ELEM/MASS,IND,FY)/ 30785 4 3 (90-TH-232(N,F)MASS,CHN,FY)) 30785 4 4 RESULT (FRIND) 30785 4 5 METHOD FROM MEASURED CUMULATIVE YIELDS AS GIVEN IN SUBENTRY 2 30785 4 6 AND LITERATURE VALUES FOR CHAIN YIELDS, A CURVE OF 30785 4 7 CHAIN YIELDS WAS OBTAINED (FIG.1 OF HIGH EN.NUCL.PHYS. 30785 4 8 11 376). 30785 4 9 TOTAL INDEPENDENT YIELDS FOR A GIVEN ELEMENT/MASS WERE 30785 4 10 OBTAINED FROM THE MEASURED INDEPENDENT YIELDS AS GIVEN 30785 4 11 IN SUBENTRY 3, AND ISOMERIC RATIOS FROM U-235 THERMAL 30785 4 12 FISSION, UNLESS STATED OTHERWISE (SEE FLAG). 30785 4 13 DECAY-DATA ((1.)45-RH-106-M,2.2HR) 30785 4 14 ((2.)47-AG-112,3.12HR) SEE COMMENT BELOW 30785 4 15 ((3.)49-IN-115-M,4.49HR) 30785 4 16 ((4.)49-IN-116-M1,54.2MIN) 30785 4 17 ((5.)51-SB-124-G,60.2D) 30785 4 18 ((6.)51-SB-126-G,12.4D) 30785 4 19 ((7.)51-SB-128-G,9.01HR) 30785 4 20 THE HALF-LIVES ARE GIVEN IN TABLE 2 OF HIGH EN.NUCL. 30785 4 21 PHYS. 11 376. IT IS ASSUMED THAT THE GAMMA-RAY DATA 30785 4 22 WERE ALSO TAKEN FROM: U.REUS ET AL, GSI 79-2 (2/1979), 30785 4 23 BUT THEY ARE NOT REPRODUCED HERE. 30785 4 24 - COMMENT: TABLE 2 OF HIGH EN.NUCL.PHYS. 11 376 GIVES 30785 4 25 'AG-112M' BUT AG-112 DOES NOT HAVE A METASTABLE STATE30785 4 26 FLAG (1.) THIS IS A LOWER LIMIT AS THE ISOMERIC RATIO IS 30785 4 27 NOT KNOWN AND THE ISOMER NOT CONSIDERED. 30785 4 28 (2.) AN UPPER LIMIT ONLY IS GIVEN AS THE GAMMA-RAY 30785 4 29 ACTIVITY WAS TOO LOW. 30785 4 30 (3.) THE ISOMERIC RATIO USED IS: YM/YG = 1.38 30785 4 31 STATUS (DEP,30785002) AND FIG.1 OF HIGH EN.NUCL.PHYS. 11 376 30785 4 32 (CHAIN YIELDS) 30785 4 33 (DEP,30785003) INDEPENDENT YIELDS 30785 4 34 DATA TAKEN FROM TABLE 2 OF HIGH EN.NUCL.PHYS. 11 376 30785 4 35 HISTORY (930125A) HW.-KEYWORD 'RESULT'ADDED, DECAY-DATA 30785 4 36 CORRECTED, DATA UNITS ALTERED.- 30785 4 37 ENDBIB 35 30785 4 38 NOCOMMON 0 0 30785 4 39 DATA 8 7 30785 4 40 ELEMENT MASS ISOMER DATA DATA-ERR DATA-MAX 30785 4 41 DECAY-FLAG FLAG 30785 4 42 NO-DIM NO-DIM NO-DIM NO-DIM NO-DIM NO-DIM 30785 4 43 NO-DIM NO-DIM 30785 4 44 45. 106. 1. 1.4E-04 0.7E-04 30785 4 45 1. 1. 30785 4 46 47. 112. 4.6E-03 1.6E-03 30785 4 47 2. 30785 4 48 49. 115. 1. 8.E-0430785 4 49 3. 2. 30785 4 50 49. 116. 1. 6.3E-03 2.5E-03 30785 4 51 4. 1. 30785 4 52 51. 124. 0. 1.9E-0330785 4 53 5. 2. 30785 4 54 51. 126. 0. 1.4E-01 0.3E-01 30785 4 55 6. 30785 4 56 51. 128. 0. 3.3E-01 0.3E-01 30785 4 57 7. 3. 30785 4 58 ENDDATA 18 30785 4 59 ENDSUBENT 8 30785 499999 ENDENTRY 4 3078599999999 ENTRY 32628 950810 32628 0 1 SUBENT 32628001 950810 32628 1 1 BIB 15 49 32628 1 2 INSTITUTE (3CPRIMP) 32628 1 3 REFERENCE (J,HFH,5,(2),176,8305) 32628 1 4 AUTHOR (LI WENXIN,SUN TONGYU,ZHEN MANJIAO,DONG TIANRONG, 32628 1 5 SUN XIUHUA) 32628 1 6 TITLE Determination of the yields for the rare-earth 32628 1 7 nuclides from 14 MeV neutron fission of U-238 using 32628 1 8 a Ge(li) detector. 32628 1 9 FACILITY (CCW) 600 kV Cockcroft Walton accelerator 32628 1 10 INC-SOURCE (D-T) 32628 1 11 Neutron flux about (1-2)*e+11 neutrons/4pi/sec, 32628 1 12 average neutron energy=14.7+-0.4 MeV 32628 1 13 SAMPLE Uranium nitrate (natural Uranium) 32628 1 14 METHOD (CHSEP,FPGAM) 32628 1 15 First, fission products were separated from the 32628 1 16 irradiated samples by radiochemistry methods and 32628 1 17 weighted for the determination of the chemical yield. 32628 1 18 then fission product gamma rays were measured with 32628 1 19 calibrated ge(li) detector for determining the 32628 1 20 cumulative fission yield. 32628 1 21 DETECTOR (GELI) A 140 cm3 coaxial Ge(li) detector, resolution 32628 1 22 was 2.8 keV at 1.332 MeV of Co-60, together with a 32628 1 23 4096 channel analyser. The relative detection 32628 1 24 efficiency was calibrated using well know intensity 32628 1 25 gamma ray sources. 32628 1 26 MONITOR (92-U-238(N,F)42-MO-99,CUM,FY) 32628 1 27 DECAY-DATA The decay data given below were used for decay 32628 1 28 correction in calculating the cumulative yields. 32628 1 29 (39-Y-93,10.1HR,DG,266.9,0.0698) 32628 1 30 (58-CE-141,32.4D,DG,145.4,0.48) 32628 1 31 (57-LA-142,1.59HR,DG,641.2,0.475,DG,894.8,0.086) 32628 1 32 (58-CE-143,1.375D,DG,293.3,0.413) 32628 1 33 (58-CE-144,284.3D,DG,133.5,0.108) 32628 1 34 (59-PR-145,5.98HR,DG,675.8,0.00375,DG,748.3,0.00427) 32628 1 35 (60-ND-147,11.1D,DG,319.4,0.0205,DG,531.0,0.133) 32628 1 36 (60-ND-149,1.73HR,DG,211.3,0.273) 32628 1 37 (61-PM-149,53.1HR,DG,285.9,0.031) 32628 1 38 (61-PM-151,28.4HR,DG,340.1,0.224) 32628 1 39 (62-SM-153,46.7HR,DG,103.2,0.283) 32628 1 40 (62-SM-156,9.4HR,DG,203.8,0.23) 32628 1 41 (63-EU-156,15.19D,DG,1230.4,0.089) 32628 1 42 (63-EU-157,15.149HR,DG,411.0,0.19) 32628 1 43 CORRECTION Made for the loss of photoelectrons due to cascade 32628 1 44 gamma rays coincidence and counting dead time. 32628 1 45 ERR-ANALYS Errors given in the data table are total experimental 32628 1 46 errors, they contain mainly the detection efficiency, 32628 1 47 least-squares fit of gamma photoelectron peak, counting32628 1 48 statistics, and correction for cascade gamma rays. 32628 1 49 STATUS Data taken from table 2 of J.HFH,5,(2),176,8305 32628 1 50 HISTORY (950810C) Compiled by Liang Qichang (CNDC) 32628 1 51 ENDBIB 49 32628 1 52 COMMON 2 3 32628 1 53 EN MONIT 32628 1 54 MEV PC/FIS 32628 1 55 14.0 5.60 32628 1 56 ENDCOMMON 2 3 32628 1 57 ENDSUBENT 2 32628 199999 SUBENT 32628002 950810 32628 2 1 BIB 2 4 32628 2 2 REACTION (92-U-238(N,F)ELEM/MASS,CUM,FY) 32628 2 3 STATUS (COREL,32628003) The data given in this subent was the 32628 2 4 experimental data which was processed by using the 32628 2 5 code GAMAPU. 32628 2 6 ENDBIB 4 32628 2 7 NOCOMMON 0 0 32628 2 8 DATA 4 14 32628 2 9 ELEMENT MASS DATA ERR-T 32628 2 10 NO-DIM NO-DIM PC/FIS PC/FIS 32628 2 11 39. 93. 4.77 0.40 32628 2 12 57. 142. 3.59 0.34 32628 2 13 58. 141. 4.44 0.41 32628 2 14 58. 143. 4.32 0.35 32628 2 15 58. 144. 4.00 0.53 32628 2 16 59. 145. 2.93 0.45 32628 2 17 60. 147. 2.44 0.36 32628 2 18 60. 149. 1.30 0.13 32628 2 19 61. 149. 2.43 0.32 32628 2 20 61. 151. 0.80 0.09 32628 2 21 62. 153. 0.83 0.21 32628 2 22 62. 156. 0.13 0.02 32628 2 23 63. 156. 0.12 0.02 32628 2 24 63. 157. 0.078 0.010 32628 2 25 ENDDATA 16 32628 2 26 ENDSUBENT 4 32628 299999 SUBENT 32628003 950810 32628 3 1 BIB 2 6 32628 3 2 REACTION (92-U-238(N,F)ELEM/MASS,CUM,FY) 32628 3 3 STATUS (COREL,32628002) The data given below was the same 32628 3 4 experimental data as above but processed by using 32628 3 5 another code GAMA81. Comparing this data with those of 32628 3 6 above subent, this data are in agreement with the 32628 3 7 other publised data better than the above subent. 32628 3 8 ENDBIB 6 32628 3 9 NOCOMMON 0 0 32628 3 10 DATA 4 14 32628 3 11 ELEMENT MASS DATA ERR-T 32628 3 12 NO-DIM NO-DIM PC/FIS PC/FIS 32628 3 13 39. 93. 4.53 0.35 32628 3 14 57. 142. 3.50 0.33 32628 3 15 58. 141. 4.25 0.36 32628 3 16 58. 143. 3.99 0.33 32628 3 17 58. 144. 3.64 0.48 32628 3 18 59. 145. 2.81 0.56 32628 3 19 60. 147. 2.18 0.21 32628 3 20 60. 149. 1.44 0.12 32628 3 21 61. 149. 1.77 0.23 32628 3 22 61. 151. 0.76 0.09 32628 3 23 62. 153. 0.77 0.18 32628 3 24 62. 156. 0.14 0.02 32628 3 25 63. 156. 0.12 0.03 32628 3 26 63. 157. 0.077 0.011 32628 3 27 ENDDATA 16 32628 3 28 ENDSUBENT 4 32628 399999 ENDENTRY 3 3262899999999 ENTRY 32630 950920 32630 0 1 SUBENT 32630001 950920 32630 1 1 BIB 16 36 32630 1 2 INSTITUTE (3CPRAEP) 32630 1 3 REFERENCE (J,HFH,2,(4),193,8011) 32630 1 4 AUTHOR (LIU CONGGUI) Fission yield group 32630 1 5 TITLE The absolute determination of cumulative yields of 32630 1 6 several nuclides from 14.9 MeV neutron-induced fission 32630 1 7 of U-238 32630 1 8 FACILITY (CCW) 600 KV Cockcroft Walton accelerator 32630 1 9 INC-SOURCE (D-T) 250 keV deuteron beam bombarding T-Ti target, 32630 1 10 thickness=0.8-1.6 mg/cm2, neutron intensity=(2-20)*e+9 32630 1 11 neutrons/sec. 32630 1 12 SAMPLE Metallic uranium foil, diameter=16 mm, 32630 1 13 weight=600-800 mg. 32630 1 14 METHOD (RCHEM) 32630 1 15 DETECTOR (FISCH) Double fission ionization chamber was used for 32630 1 16 fission rate absolute measurement. 32630 1 17 (NAICR,GEMUC) the NaI(tl) crystal detector was used for32630 1 18 gamma detection and low-background 2pi beta counter 32630 1 19 was used for beta detection. 32630 1 20 PART-DET (G,B) 32630 1 21 MONITOR Absolute measurement 32630 1 22 DECAY-DATA No information given 32630 1 23 CORRECTION Correction has made for fission induced by low energy 32630 1 24 neutrons which were from experimental hall scattering 32630 1 25 and d-d reaction. 32630 1 26 ERR-ANALYS Total error was given, it consists of: 32630 1 27 . accidental error (statistical error) and 32630 1 28 . systematic error (2.1-3.7 percent) which mainly 32630 1 29 including the detector efficiency error 32630 1 30 (1.5-3.3 percent) and fission rate measurement error 32630 1 31 (1.5 percent). the errors due to the correction for 32630 1 32 fission yield contributed by the experimental hall 32630 1 33 scattering neutrons and d-d neutrons and sample 32630 1 34 weight determination as well as the decay constant 32630 1 35 can be neglected. 32630 1 36 STATUS Data taken from table 3 of J,HFH,VOL.2,NO.4,P.193,8011.32630 1 37 HISTORY (950915C) Compiled by Liang Qichang, CNDC. 32630 1 38 ENDBIB 36 32630 1 39 COMMON 2 3 32630 1 40 EN EN-ERR 32630 1 41 MEV MEV 32630 1 42 14.9 0.46 32630 1 43 ENDCOMMON 2 3 32630 1 44 ENDSUBENT 2 32630 199999 SUBENT 32630002 950915 32630 2 1 BIB 1 1 32630 2 2 REACTION (92-U-238(N,F)ELEM/MASS,CUM,FY) 32630 2 3 ENDBIB 1 32630 2 4 NOCOMMON 0 0 32630 2 5 DATA 4 6 32630 2 6 ELEMENT MASS DATA ERR-T 32630 2 7 NO-DIM NO-DIM PC/FIS PC/FIS 32630 2 8 40. 95. 4.96 0.22 32630 2 9 42. 99. 5.44 0.20 32630 2 10 44. 103. 4.75 0.23 32630 2 11 44. 106. 2.51 0.13 32630 2 12 58. 144. 4.01 0.21 32630 2 13 60. 147. 2.13 0.11 32630 2 14 ENDDATA 8 32630 2 15 ENDSUBENT 4 32630 299999 ENDENTRY 2 3263099999999 ENTRY 32631 951020 32631 0 1 SUBENT 32631001 951020 32631 1 1 BIB 14 20 32631 1 2 INSTITUTE (3CPRAEP) 32631 1 3 REFERENCE (J,HFH,6,(4),229,8411) 32631 1 4 AUTHOR (WANG XIUZHI,LI ZE) Cumulative yield group 32631 1 5 TITLE The absolute determination of cumulative yield of 32631 1 6 several nuclides from 14.9 MeV neutron-induced fission 32631 1 7 of U-235. 32631 1 8 FACILITY (CCW) 600 kV Cockroft-Walton ACCELERATOR 32631 1 9 INC-SOURCE (D-T) A rotating tritium target is used and the neutron32631 1 10 flux is 2*E+10 neutrons/sec. 32631 1 11 SAMPLE U3O8 powder of enriched uranium (90 percent for U-235).32631 1 12 METHOD (RCHEM) 32631 1 13 DETECTOR (FISCH) The absolute fission rate of the sample was 32631 1 14 measured by double fission ionization chamber. 32631 1 15 MONITOR Absolute measurement. 32631 1 16 DECAY-DATA No information given. 32631 1 17 ERR-ANALYS Total error including statistical and systematic errors32631 1 18 was given. 32631 1 19 STATUS Data and errors taken from table 1 and 2 respectively 32631 1 20 of J.HFH,VOL.6,NO.4,P.229,8411. 32631 1 21 HISTORY (951020C) Compiled by Liang Qichang,CNDC. 32631 1 22 ENDBIB 20 32631 1 23 COMMON 1 3 32631 1 24 EN 32631 1 25 MEV 32631 1 26 14.9 32631 1 27 ENDCOMMON 1 3 32631 1 28 ENDSUBENT 1 32631 199999 SUBENT 32631002 951020 32631 2 1 BIB 1 1 32631 2 2 REACTION (92-U-235(N,F)ELEM/MASS,CUM,FY) 32631 2 3 ENDBIB 1 32631 2 4 NOCOMMON 0 0 32631 2 5 DATA 4 9 32631 2 6 ELEMENT MASS DATA ERR-T 32631 2 7 NO-DIM NO-DIM PC/FIS PC/FIS 32631 2 8 40. 95. 5.28 0.21 32631 2 9 40. 97. 5.12 0.23 32631 2 10 42. 99. 5.36 0.23 32631 2 11 44. 103. 3.31 0.13 32631 2 12 44. 106. 1.84 0.14 32631 2 13 56. 140. 4.76 0.39 32631 2 14 58. 143. 3.78 0.18 32631 2 15 58. 144. 3.30 0.13 32631 2 16 60. 147. 1.59 0.10 32631 2 17 ENDDATA 11 32631 2 18 ENDSUBENT 4 32631 299999 ENDENTRY 2 3263199999999 ENTRY 32634 951220 32634 0 1 SUBENT 32634001 951220 32634 1 1 BIB 15 40 32634 1 2 INSTITUTE (3CPRIMP) 32634 1 3 REFERENCE (J,HFH,2,(1),9,8002) 32634 1 4 AUTHOR (LI WENXIN,SUN TONGYU,SUN XIUHUA,ZHANG TIANMEI, 32634 1 5 ZHENG MANJIAO,DONG TIANRONG,FU MING) 32634 1 6 TITLE Charge distribution in the fission of U-238 by 14.7 MeV32634 1 7 neutrons. 32634 1 8 FACILITY (CCW) 32634 1 9 INC-SOURCE (D-T) 300 keV deuteron beam bombarding the T-Ti target,32634 1 10 neutron intensity was 2*E+11 neutrons/sec in general 32634 1 11 and 4.8*E+11 neutrons/sec for rotating T-Ti target. 32634 1 12 SAMPLE UO2(NO3)2.6H2O 32634 1 13 METHOD (CHSEP) 32634 1 14 First,fission products were separated from the 32634 1 15 irradiated sample by radiochemistry methods and weighed32634 1 16 for the determination of the chemical yield. Then 32634 1 17 fission product gamma rays were measured with 32634 1 18 calibrated Ge(li) detector. 32634 1 19 DETECTOR (GELI) Resolution was 8.0 keV for 1.332 MeV gamma ray 32634 1 20 of Co-60. 32634 1 21 MONITOR (92-U-238(N,F)42-MO-99,CUM,FY) 32634 1 22 MONIT-REF (,D.E.ADAMS+,J,JIN,37,419,7501) 32634 1 23 DECAY-DATA The decay data given below were used for decay 32634 1 24 correction in calculating the fission yields. 32634 1 25 (35-BR-82-G,35.5HR,DG,554.3,0.704,DG,776.5,0.833) 32634 1 26 (40-ZR-95,63.98D,DG,724.2,0.43) 32634 1 27 (40-ZR-97,16.82HR,DG,743.4,0.94) 32634 1 28 (42-MO-99,66.02HR,DG,140.5,0.90) 32634 1 29 (53-I-131,8.022D,DG,364.5,0.79) 32634 1 30 (53-I-132-G,2.28HR,DG,667.7,0.98) 32634 1 31 (53-I-133-G,21.0HR,DG,529.5,0.87) 32634 1 32 (53-I-134-G,53.2MIN,DG,847.1,0.957) 32634 1 33 (53-I-135,6.61HR,DG,1260.4,0.284) 32634 1 34 (55-CS-136-G,13.0D,DG,818.5,1.0,DG,1048.1,0.805) 32634 1 35 (55-CS-138-G,33.41MIN,DG,462.7,0.270) 32634 1 36 (57-LA-140,40.22HR,DG,1596.4,0.96) 32634 1 37 (57-LA-142,1.545HR,DG,641.2,0.465) 32634 1 38 CORRECTION No information given 32634 1 39 ERR-ANALYS Errors given in the data table are total experimental 32634 1 40 errors. 32634 1 41 HISTORY (951220C) Compiled by Liang Qichang, CNDC 32634 1 42 ENDBIB 40 32634 1 43 COMMON 2 3 32634 1 44 EN MONIT 32634 1 45 MEV PC/FIS 32634 1 46 14.7 5.6 32634 1 47 ENDCOMMON 2 3 32634 1 48 ENDSUBENT 2 32634 199999 SUBENT 32634002 951220 32634 2 1 BIB 3 4 32634 2 2 REACTION (92-U-238(N,F)ELEM/MASS,CUM,FY) 32634 2 3 CORRECTION In order to obtain the cumulative yield of I-134, 32634 2 4 corrections were made for its precursor decay. 32634 2 5 STATUS Data taken from table 2 of J, HFH,VOL.2,NO.1,P.9,8002. 32634 2 6 ENDBIB 4 32634 2 7 NOCOMMON 0 0 32634 2 8 DATA 4 9 32634 2 9 ELEMENT MASS DATA ERR-T 32634 2 10 NO-DIM NO-DIM PC/FIS PC/FIS 32634 2 11 40. 95. 5.00 0.55 32634 2 12 40. 97. 4.95 0.40 32634 2 13 42. 99. 5.60 32634 2 14 53. 131. 3.76 0.30 32634 2 15 53. 133. 6.36 0.45 32634 2 16 53. 134. 5.63 0.56 32634 2 17 53. 135. 5.13 0.36 32634 2 18 55. 138. 5.06 0.35 32634 2 19 57. 142. 3.96 0.28 32634 2 20 ENDDATA 11 32634 2 21 ENDSUBENT 4 32634 299999 SUBENT 32634003 951220 32634 3 1 BIB 2 2 32634 3 2 REACTION (92-U-238(N,F)ELEM/MASS,IND,FY) 32634 3 3 STATUS Data taken from table 3 of J,HFH,VOL.2,NO.1,P.9,8002. 32634 3 4 ENDBIB 2 32634 3 5 NOCOMMON 0 0 32634 3 6 DATA 4 4 32634 3 7 ELEMENT MASS DATA ERR-T 32634 3 8 NO-DIM NO-DIM PC/FIS PC/FIS 32634 3 9 35. 82. 7.5E-05 1.7E-05 32634 3 10 53. 132. 1.7E-01 0.4E-01 32634 3 11 55. 136. 1.6E-02 0.1E-02 32634 3 12 57. 140. 4.3E-03 2.1E-03 32634 3 13 ENDDATA 6 32634 3 14 ENDSUBENT 4 32634 399999 SUBENT 32634004 951220 32634 4 1 BIB 3 14 32634 4 2 REACTION ((92-U-238(N,F)ELEM/MASS,IND,FY)/ 32634 4 3 (92-U-238(N,F)MASS,CHN,FY)) 32634 4 4 COMMENT In order to convert the independent yield into 32634 4 5 fractional independent yield, it needs the mass yield, 32634 4 6 which were obtained from the cumulative yield measured 32634 4 7 by author and other published cumulative yield. 32634 4 8 In this subentry, for Br-82, the fractional independent32634 4 9 yield (1.3+-0.3)*E-4 was larger than the independent 32634 4 10 yield (7.5+-1.7)*E-5 presented in above 32634 4 11 subentry (32634003).This seems unreasonable,so one of 32634 4 12 these two values should be wrong. Unfortunately the 32634 4 13 compiler cannot contact with authors, so users should 32634 4 14 be careful when use the values for Br-82. 32634 4 15 STATUS Data taken from table 3 of J,HFH,VOL.2, NO.1,P.9,8002. 32634 4 16 ENDBIB 14 32634 4 17 NOCOMMON 0 0 32634 4 18 DATA 4 4 32634 4 19 ELEMENT MASS DATA ERR-T 32634 4 20 NO-DIM NO-DIM NO-DIM NO-DIM 32634 4 21 35. 82. 1.3E-04 0.3E-04 32634 4 22 53. 132. 3.5E-02 0.9E-02 32634 4 23 55. 136. 3.1E-03 0.3E-03 32634 4 24 57. 140. 8.8E-04 4.4E-04 32634 4 25 ENDDATA 6 32634 4 26 ENDSUBENT 4 32634 499999 ENDENTRY 4 3263499999999 ENTRY 32636 960105 32636 0 1 SUBENT 32636001 960105 32636 1 1 BIB 16 102 32636 1 2 INSTITUTE (3CPRIMP) 32636 1 3 REFERENCE (J,PHE,12,(2),221,8805) 32636 1 4 AUTHOR (SUN TONGYU,LI WENXIN,DONG TIANRONG,FU MING) 32636 1 5 TITLE Mass distribution in the 14.7 MeV neutron-induced 32636 1 6 fission of Th-232 32636 1 7 FACILITY (CCW) 600 kV Cockcroft Walton accelerator 32636 1 8 INC-SOURCE (D-T) Neutron intensity 2*E+11 neutrons/sec 32636 1 9 SAMPLE Analytically pure thorium nitrate, weight 800 mg for 32636 1 10 measurement by using direct gamma ray spectrometry, 32636 1 11 and 6 grams for measurement by using chemical 32636 1 12 separation followed by gamma ray spectrometry. 32636 1 13 METHOD (FPGAM) The direct gamma ray spectrometry method was 32636 1 14 used for measuring most fission products in this work. 32636 1 15 (CHSEP,GSPEC) For the long half-life fission products 32636 1 16 Ru-103,Ru-106,Sb-125 and Cs-137. The yields were 32636 1 17 determined by chemical separation followed by gamma 32636 1 18 ray spectrometry. 32636 1 19 DETECTOR (GELI) Ge(li) detector volume: 60cm3;resolution (fwhm) 32636 1 20 was 2.0 keV at 1332 keV gamma ray for Co-60. The 32636 1 21 efficiency was calibrated with a series of standard 32636 1 22 gamma sources provided by China Institute of Atomic 32636 1 23 Energy. 32636 1 24 MONITOR (90-TH-232(N,F)42-MO-99,CUM,FY) 32636 1 25 MONIT-REF (,V.A.VLASOV,R,AEC-TR-4665,6001) 32636 1 26 DECAY-DATA The decay data given below were used for calculating 32636 1 27 the fission yields. This list includes the fission 32636 1 28 products measured and their precursors. 32636 1 29 (32-GE-77-G,11.3HR,DG,210.8,0.304) 32636 1 30 (32-GE-78,1.45HR,DG,277.3,0.96) 32636 1 31 (34-SE-83-G,22.5MIN,DG,356.7,0.686) 32636 1 32 (35-BR-84-G,31.8MIN,DG,881.6,0.416) 32636 1 33 (36-KR-85-M,4.48HR,DG,151.0,0.752,DG,304.5,0.14) 32636 1 34 (36-KR-87,76.4MIN,DG,402.7,0.497) 32636 1 35 (36-KR-88,2.84HR,DG,196.3,0.263,DG,834.8,0.131) 32636 1 36 (37-RB-89,15.4MIN,DG,1031.9,0.636,DG,1248.1,0.467) 32636 1 37 (38-SR-91,9.48HR,DG,749.8,0.23,DG,1024.3,0.325) 32636 1 38 (38-SR-92,2.71HR,DG,430.6,0.033,DG,1383.9,0.90) 32636 1 39 (39-Y-93,10.1HR,DG,266.9,0.0698,DG,947.1,0.0194) 32636 1 40 (39-Y-94,19.0MIN,DG,919.2,0.49) 32636 1 41 (40-ZR-95,64.0D,DG,756.7,0.554) 32636 1 42 (40-ZR-97,17.0HR,DG,657.9,,DG,743.4,0.927) 32636 1 43 (42-MO-99,66.0HR,DG,181.1,0.0682) 32636 1 44 (43-TC-99-M,6.02HR,DG,140.5,0.876) 32636 1 45 (42-MO-101,14.6MIN) 32636 1 46 (43-TC-101,14.2MIN,DG,306.8,0.882) 32636 1 47 (44-RU-103,39.4D,DG,497.1,0.864) 32636 1 48 (44-RU-105,4.44HR,DG,469.4,0.176,DG,676.4,0.157, 32636 1 49 DG,724.2,0.476) 32636 1 50 (44-RU-106,368.0D,DG,511.8,0.206) 32636 1 51 (45-RH-107,21.7MIN,DG,302.8,0.67) 32636 1 52 (47-AG-111-G,7.47D,DG,342.1,0.0668) 32636 1 53 (46-PD-112,21.05HR,DG,617.4,0.499,DG,1387.7,0.0624) 32636 1 54 (47-AG-113-G,5.37HR,DG,298.4,0.0946,DG,316.1,0.0129) 32636 1 55 (48-CD-115-G,53.5HR,DG,336.3,0.497,DG,492.4,0.0803, 32636 1 56 DG,527.9,0.275) 32636 1 57 (48-CD-117-M,3.4HR,DG,158.6,,DG,552.9) 32636 1 58 (48-CD-117-G,2.4HR,DG,273.3,0.29,DG,344.5,0.177) 32636 1 59 (50-SN-123-M,40.1MIN,DG,160.3,0.854) 32636 1 60 (50-SN-125-G,9.64D,DG,915.5,0.039) 32636 1 61 (50-SN-125-M,9.52MIN,DG,331.9,0.948) 32636 1 62 (51-SB-125,2.77YR,DG,427.9,0.304) 32636 1 63 (50-SN-127-G,2.1HR,DG,1095.6,0.19,DG,1114.3,0.38) 32636 1 64 (51-SB-127,3.85D,DG,473.0,0.25,DG,685.7,0.357) 32636 1 65 (50-SN-128-G,59.1MIN,DG,482.3,0.58) 32636 1 66 (51-SB-128-G,9.01HR,DG,754.0,1.0) 32636 1 67 (51-SB-129-G,4.32HR,DG,544.7,0.181,DG,812.8,0.435) 32636 1 68 (51-SB-130-G,40.0MIN,DG,330.9,0.78,DG,793.4,1.0) 32636 1 69 (51-SB-131,23.0MIN,DG,943.4,0.44) 32636 1 70 (53-I-131,8.04D,DG,364.5,0.812,DG,637.0,0.0727) 32636 1 71 (52-TE-132,78.2HR,DG,228.2,0.881,DG,667.7,, 32636 1 72 DG,772.1,0.787) 32636 1 73 (52-TE-133-M,55.4MIN,DG,647.4,0.156,DG,912.6,0.458) 32636 1 74 (53-I-133-G,20.8HR,DG,529.9,0.87,DG,875.3,0.0451) 32636 1 75 (52-TE-134,41.8MIN,DG,278.0,0.217) 32636 1 76 (53-I-134-G,52.6MIN,DG,595.4,0.114,DG,847.0,0.954, 32636 1 77 DG,884.1,0.653,DG,1072.5,0.153) 32636 1 78 (53-I-135,6.61HR,DG,1131.5,0.225,DG,1260.4,0.286) 32636 1 79 (55-CS-137,30.2YR,DG,661.6,0.851) 32636 1 80 (54-XE-138,14.1MIN,DG,258.3,0.315) 32636 1 81 (55-CS-138-G,32.2MIN,DG,462.8,0.307,DG,1009.8,0.298, 32636 1 82 DG,1435.9,0.763) 32636 1 83 (56-BA-139,1.42HR,DG,165.8,0.188) 32636 1 84 (56-BA-140,12.79D,DG,537.3,0.24) 32636 1 85 (57-LA-140,40.2HR,DG,487.0,0.43,DG,1596.5,0.955) 32636 1 86 (58-CE-141,32.5D,DG,145.4,0.484) 32636 1 87 (57-LA-141,3.93HR,DG,1354.3,0.0263) 32636 1 88 (57-LA-142,1.55HR,DG,641.2,0.53,DG,894.8,0.094) 32636 1 89 (58-CE-143,33.0HR,DG,293.3,0.434) 32636 1 90 (59-PR-146,24.1MIN,DG,453.8,0.48) 32636 1 91 (60-ND-147,11.1D,DG,531.0,0.133) 32636 1 92 (60-ND-149,1.73HR,DG,211.3,0.273,DG,270.2,0.107) 32636 1 93 (61-PM-151,28.4HR,DG,340.1,0.224) 32636 1 94 CORRECTION Corrections were made for gamma self-absorption in the 32636 1 95 sample. In the gamma energy range of considered 32636 1 96 fission products, the correction factor was 0.89-1.0. 32636 1 97 ERR-ANALYS The experimental standard deviation were given. The 32636 1 98 largest error was from the statistical counting of weak32636 1 99 gamma peak. The quoted absolute gamma ray intensity 32636 1 100 also can cause large uncertainty but is not included in32636 1 101 the given error. 32636 1 102 STATUS Data taken from table 2 of J,PHE,VOL.12,NO.2,P.221,880532636 1 103 HISTORY (960105C) Compiled by Liang Qichang, CNDC. 32636 1 104 ENDBIB 102 32636 1 105 COMMON 3 3 32636 1 106 EN EN-ERR MONIT 32636 1 107 MEV MEV PC/FIS 32636 1 108 14.7 0.4 2.0 32636 1 109 ENDCOMMON 3 3 32636 1 110 ENDSUBENT 3 32636 199999 SUBENT 32636002 960105 32636 2 1 BIB 2 6 32636 2 2 REACTION (90-TH-232(N,F)ELEM/MASS,CUM,FY) 32636 2 3 FLAG (1.) Only one isomer was measured in this experiment. 32636 2 4 (2.) Data taken from the experimental results of 32636 2 5 chemical separation. The Ru-105 was used for 32636 2 6 reference nuclide, then the results were normalized 32636 2 7 to those obtained by direct gamma ray spectrometry. 32636 2 8 ENDBIB 6 32636 2 9 NOCOMMON 0 0 32636 2 10 DATA 6 56 32636 2 11 ELEMENT MASS ISOMER DATA DATA-ERR FLAG 32636 2 12 NO-DIM NO-DIM NO-DIM PC/FIS PC/FIS NO-DIM 32636 2 13 32. 77. 0. 0.03 0.01 32636 2 14 32. 78. 0.17 0.08 32636 2 15 34. 83. 0. 1.00 0.22 1. 32636 2 16 35. 84. 3.76 0.43 32636 2 17 36. 85. 1. 3.80 0.17 32636 2 18 36. 87. 4.57 0.23 32636 2 19 36. 88. 4.58 0.31 32636 2 20 37. 89. 5.36 0.28 32636 2 21 38. 91. 5.71 0.31 32636 2 22 38. 92. 5.31 0.19 32636 2 23 39. 93. 5.44 0.28 32636 2 24 39. 94. 5.09 0.27 32636 2 25 40. 95. 4.95 0.26 32636 2 26 40. 97. 3.75 0.11 32636 2 27 42. 99. 2.27 0.20 32636 2 28 42. 101. 1.51 0.17 32636 2 29 44. 103. 0.87 0.09 2. 32636 2 30 44. 105. 1.01 0.04 32636 2 31 44. 106. 1.11 0.14 2. 32636 2 32 45. 107. 0.97 0.27 32636 2 33 46. 112. 1.72 0.06 32636 2 34 47. 111. 0. 1.55 0.09 32636 2 35 47. 113. 0. 1.53 0.07 32636 2 36 48. 115. 0. 1.40 0.05 32636 2 37 48. 117. 0. 0.79 0.06 32636 2 38 48. 117. 1. 0.67 0.10 32636 2 39 50. 123. 1. 0.55 0.06 1. 32636 2 40 50. 125. 0. 0.48 0.18 32636 2 41 50. 125. 1. 0.50 0.25 32636 2 42 50. 127. 0. 0.77 0.035 32636 2 43 50. 128. 0.69 0.05 32636 2 44 51. 125. 0.80 0.07 32636 2 45 51. 127. 1.15 0.07 32636 2 46 51. 128. 0. 0.24 0.02 32636 2 47 51. 129. 1.14 0.06 32636 2 48 51. 130. 0. 0.58 0.03 1. 32636 2 49 51. 131. 2.06 0.19 32636 2 50 52. 132. 3.55 0.16 32636 2 51 52. 133. 1. 2.72 0.21 1. 32636 2 52 52. 134. 4.93 0.17 32636 2 53 53. 131. 2.18 0.27 32636 2 54 53. 133. 0. 5.16 0.22 32636 2 55 53. 135. 5.24 0.18 32636 2 56 54. 138. 5.80 0.30 32636 2 57 55. 137. 5.81 0.41 2. 32636 2 58 55. 138. 0. 5.47 0.58 32636 2 59 56. 139. 6.13 0.52 32636 2 60 56. 140. 5.91 0.52 32636 2 61 57. 141. 4.28 0.21 32636 2 62 57. 142. 5.62 0.16 32636 2 63 58. 141. 4.53 0.49 32636 2 64 58. 143. 5.29 0.70 32636 2 65 58. 145. 2.79 0.52 32636 2 66 60. 147. 1.64 0.16 32636 2 67 60. 149. 0.61 0.03 32636 2 68 61. 151. 0.20 0.01 32636 2 69 ENDDATA 58 32636 2 70 ENDSUBENT 6 32636 299999 SUBENT 32636003 960105 32636 3 1 BIB 2 4 32636 3 2 REACTION (90-TH-232(N,F)MASS,CHN,FY) 32636 3 3 FLAG (1.) The yields were calculated according to the beta 32636 3 4 decay of precursor or the transition branch ratio 32636 3 5 of isomer. 32636 3 6 ENDBIB 4 32636 3 7 NOCOMMON 0 0 32636 3 8 DATA 4 10 32636 3 9 MASS DATA DATA-ERR FLAG 32636 3 10 NO-DIM PC/FIS PC/FIS NO-DIM 32636 3 11 77. 0.16 0.06 1. 32636 3 12 113. 1.69 0.13 1. 32636 3 13 115. 1.58 0.05 1. 32636 3 14 117. 1.45 0.12 1. 32636 3 15 125. 0.80 0.07 32636 3 16 128. 1.20 0.09 1. 32636 3 17 131. 2.18 0.27 32636 3 18 134. 5.51 0.31 32636 3 19 138. 5.64 0.44 32636 3 20 141. 4.53 0.49 32636 3 21 ENDDATA 12 32636 3 22 ENDSUBENT 4 32636 399999 SUBENT 32636004 960105 32636 4 1 BIB 1 1 32636 4 2 REACTION (90-TH-232(N,F)53-I-134,IND,FY) 32636 4 3 ENDBIB 1 32636 4 4 NOCOMMON 0 0 32636 4 5 DATA 2 1 32636 4 6 DATA DATA-ERR 32636 4 7 PC/FIS PC/FIS 32636 4 8 0.98 0.19 32636 4 9 ENDDATA 3 32636 4 10 ENDSUBENT 2 32636 499999 ENDENTRY 4 3263699999999 ENTRY 40001 19970519 40001 0 1 SUBENT 40001001 19970519 40001 1 1 BIB 8 11 40001 1 2 INSTITUTE (4RUSRI) 40001 1 3 REFERENCE (97TRIEST) 40001 1 4 AUTHOR (V.EISMONT,A.KIREEV,I.RYZHOV,G.TUTIN,K.ELMGREN, 40001 1 5 H.CONDE,J.RAHM,J.BLOMGREN,N.OLSSON,E.RAMSTROM) 40001 1 6 TITLE FISSIM FRAGMENT ANGULAR AND KINETIC ENERGY 40001 1 7 DISTRIBUTIONS FOR NEUTRON-INDUCED FISSION OF BI-209 AND40001 1 8 U-238 AT 75 MEV 40001 1 9 FACILITY (CYCLO) EP=78.1MEV 40001 1 10 INC-SOURCE (P-LI7) 7LI(P,N),EN=75MEV. 40001 1 11 METHOD (TOF) 40001 1 12 DETECTOR (IOCH) BACK TO BACK IONIZATION CHAMBER WITH FRISH GRIDS40001 1 13 ENDBIB 11 0 40001 1 14 COMMON 1 3 40001 1 15 EN 40001 1 16 MEV 40001 1 17 75.0 40001 1 18 ENDCOMMON 3 0 40001 1 19 ENDSUBENT 18 0 40001 199999 SUBENT 40001002 19970519 40001 2 1 BIB 1 4 40001 2 2 REACTION 1)(92-U-238(N,F)ELEM/MASS,,DA/FF) 40001 2 3 2)(92-U-238(P,F)ELEM/MASS,,DA/FF) 40001 2 4 AN ISOTROPY OF THE FISSION FRAGMENTS 40001 2 5 SIGMA(0 DEG)/SIGMA(90 DEG) 40001 2 6 ENDBIB 4 0 40001 2 7 NOCOMMON 0 0 40001 2 8 DATA 4 1 40001 2 9 DATA 1DATA-ERR1 DATA 2DATA-ERR2 40001 2 10 NO-DIM NO-DIM NO-DIM NO-DIM 40001 2 11 1.22 0.06 1.12 0.02 40001 2 12 ENDDATA 3 0 40001 2 13 ENDSUBENT 12 0 40001 299999 SUBENT 40001003 19970519 40001 3 1 BIB 1 4 40001 3 2 REACTION 1)(83-BI-209(N,F)ELEM/MASS,,DA/FF) 40001 3 3 2)(83-BI-209(P,F)ELEM/MASS,,DA/FF) 40001 3 4 AN ISOTIOPY OF THE FISSION FRAGMENTS 40001 3 5 SIGMA(0 DEG)/SIGMA(90 DEG) 40001 3 6 ENDBIB 4 0 40001 3 7 NOCOMMON 0 0 40001 3 8 DATA 4 1 40001 3 9 DATA 1DATA-ERR1 DATA 2DATA-ERR2 40001 3 10 NO-DIM NO-DIM NO-DIM NO-DIM 40001 3 11 1.502 0.2 1.27 0.03 40001 3 12 ENDDATA 3 0 40001 3 13 ENDSUBENT 12 0 40001 399999 ENDENTRY 3 0 4000199999999 ENTRY 40112 850329 40112 0 1 SUBENT 40112001 850329 40112 1 1 BIB 11 29 40112 1 2 INSTITUTE (4CCPFEI) 40112 1 3 REFERENCE (J,YF,14,(5),935,7105) 40112 1 4 (W,SURIN,71) DATA RECEIVED FROM AUTHOR 40112 1 5 AUTHOR (V.M.SURIN,A.I.SERGACHEV,N.I.REZCHIKOV,B.D.KUZ MINOV) 40112 1 6 TITLE YIELDS AND KINETIC ENERGIES OF FRAGMENTS AT THE FISSION40112 1 7 OF U-233 AND PU-239 BY 5.5 AND 15 MEV NEUTRONS 40112 1 8 FACILITY (VDG) VAN DE GRAAFF 40112 1 9 INC-SOURCE (P-T) PROTON-TRITIUM REACTION 40112 1 10 (D-D) DEUTERON-DEUTERIUM REACTION 40112 1 11 METHOD (COINC) COINCIDENCE BETWEEN THE FRAGMENTS 40112 1 12 DETECTOR (SOLST) SILICON DETECTOR 40112 1 13 MONITOR (92-U-235(N,F),PRE,FY) 40112 1 14 (92-U-235(N,F),,KE,FF) 40112 1 15 MASS AND ENERGY DISTRIBUTIONS 40112 1 16 OF FRAGMENTS AT THE FISSION OF U-235 BY THERMAL 40112 1 17 NEUTRONS WERE USED ON THE GRADUATION OF ENERGY SCALE 40112 1 18 OF THE ANALYSER. 40112 1 19 ERR-ANALYS STATISTICAL ERRORS OF MASS AND ENERGY DISTRIBUTIONS 40112 1 20 OF FRAGMENTS ARE EQUAL,RESPECTIVELY 40112 1 21 EPS(YM)=10*(YM/N)**(1/2) 40112 1 22 EPS(EK)=100/(YM*N)**(1/2) 40112 1 23 HERE YM- A MASS-YIELD OF FRAGMENTS WITH GIVEN 40112 1 24 MASS M 40112 1 25 EK- AVERAGE KINETIC ENERGY OF FRAGMENTS 40112 1 26 WITH GIVEN MASS M 40112 1 27 N- A NUMBER OF THE REGISTERED FRAGMENTS 40112 1 28 AT THE FISSION OF U-233 AND PU-239 40112 1 29 BY NEUTRONS 40112 1 30 HISTORY (731120C) 40112 1 31 ENDBIB 29 40112 1 32 NOCOMMON 0 0 40112 1 33 ENDSUBENT 0 40112 199999 SUBENT 40112006 850329 40112 6 1 BIB 1 1 40112 6 2 REACTION (92-U-233(N,F),PRE,FY) 40112 6 3 ENDBIB 1 40112 6 4 COMMON 1 3 40112 6 5 EN 40112 6 6 MEV 40112 6 7 1.5000E+01 40112 6 8 ENDCOMMON 1 3 40112 6 9 DATA 3 42 40112 6 10 MASS DATA DATA-ERR 40112 6 11 NO-DIM PC/FIS PC/FIS 40112 6 12 1.1700E+02 6.5000E-02 40112 6 13 1.1800E+02 6.0000E-02 40112 6 14 1.1900E+02 6.1000E-02 9.0000E-03 40112 6 15 1.2000E+02 6.4000E-02 40112 6 16 1.2100E+02 7.1000E-02 40112 6 17 1.2200E+02 9.6000E-02 40112 6 18 1.2300E+02 1.2300E-01 40112 6 19 1.2400E+02 1.4800E-01 1.6000E-02 40112 6 20 1.2500E+02 2.0500E-01 40112 6 21 1.2600E+02 3.2700E-01 40112 6 22 1.2700E+02 5.9500E-01 40112 6 23 1.2800E+02 1.0540E+00 40112 6 24 1.2900E+02 1.6050E+00 4.7000E-02 40112 6 25 1.3000E+02 2.2870E+00 40112 6 26 1.3100E+02 2.9620E+00 40112 6 27 1.3200E+02 3.6660E+00 40112 6 28 1.3300E+02 4.3470E+00 40112 6 29 1.3400E+02 4.9440E+00 8.2000E-02 40112 6 30 1.3500E+02 5.4430E+00 40112 6 31 1.3600E+02 5.7860E+00 40112 6 32 1.3700E+02 6.1510E+00 40112 6 33 1.3800E+02 6.4760E+00 40112 6 34 1.3900E+02 6.6050E+00 9.5000E-02 40112 6 35 1.4000E+02 6.6120E+00 40112 6 36 1.4100E+02 6.6180E+00 40112 6 37 1.4200E+02 6.4120E+00 40112 6 38 1.4300E+02 5.9000E+00 40112 6 39 1.4400E+02 5.0040E+00 8.3000E-02 40112 6 40 1.4500E+02 4.1740E+00 40112 6 41 1.4600E+02 3.3670E+00 40112 6 42 1.4700E+02 2.5780E+00 40112 6 43 1.4800E+02 1.9370E+00 40112 6 44 1.4900E+02 1.3890E+00 4.4700E-02 40112 6 45 1.5000E+02 9.7100E-01 40112 6 46 1.5100E+02 6.7600E-01 40112 6 47 1.5200E+02 4.6100E-01 40112 6 48 1.5300E+02 3.0700E-01 40112 6 49 1.5400E+02 2.0300E-01 1.6900E-02 40112 6 50 1.5500E+02 1.2500E-01 40112 6 51 1.5600E+02 6.6000E-02 40112 6 52 1.5700E+02 3.6000E-02 40112 6 53 1.5800E+02 2.3000E-02 40112 6 54 ENDDATA 44 40112 6 55 ENDSUBENT 3 40112 699999 SUBENT 40112012 850329 40112 12 1 BIB 1 1 40112 12 2 REACTION (94-PU-239(N,F),PRE,FY) 40112 12 3 ENDBIB 1 40112 12 4 COMMON 1 3 40112 12 5 EN 40112 12 6 MEV 40112 12 7 1.5000E+01 40112 12 8 ENDCOMMON 1 3 40112 12 9 DATA 3 41 40112 12 10 MASS DATA DATA-ERR 40112 12 11 NO-DIM PC/FIS PC/FIS 40112 12 12 1.2000E+02 7.2000E-02 40112 12 13 1.2100E+02 8.0000E-01 1.2000E-02 40112 12 14 1.2200E+02 9.4000E-02 40112 12 15 1.2300E+02 1.1700E-01 40112 12 16 1.2400E+02 1.5000E-01 40112 12 17 1.2500E+02 2.2000E-01 40112 12 18 1.2600E+02 3.4600E-01 2.4000E-02 40112 12 19 1.2700E+02 5.8500E-01 40112 12 20 1.2800E+02 9.9100E-01 40112 12 21 1.2900E+02 1.4700E+00 40112 12 22 1.3000E+02 2.1830E+00 40112 12 23 1.3100E+02 2.9660E+00 6.9000E-02 40112 12 24 1.3200E+02 3.6720E+00 40112 12 25 1.3300E+02 4.4180E+00 40112 12 26 1.3400E+02 5.1440E+00 40112 12 27 1.3500E+02 5.6300E+00 40112 12 28 1.3600E+02 5.9420E+00 9.9000E-02 40112 12 29 1.3700E+02 6.0730E+00 40112 12 30 1.3800E+02 6.0600E+00 40112 12 31 1.3900E+02 5.9250E+00 40112 12 32 1.4000E+02 5.7510E+00 40112 12 33 1.4100E+02 5.5140E+00 9.5000E-02 40112 12 34 1.4200E+02 5.1710E+00 40112 12 35 1.4300E+02 4.7910E+00 40112 12 36 1.4400E+02 4.4700E+00 40112 12 37 1.4500E+02 4.0450E+00 40112 12 38 1.4600E+02 3.5020E+00 7.6000E-02 40112 12 39 1.4700E+02 2.9540E+00 40112 12 40 1.4800E+02 2.4570E+00 40112 12 41 1.4900E+02 2.0090E+00 40112 12 42 1.5000E+02 1.6560E+00 40112 12 43 1.5100E+02 1.3400E+00 4.7000E-02 40112 12 44 1.5200E+02 1.0750E+00 40112 12 45 1.5300E+02 8.6100E-01 40112 12 46 1.5400E+02 6.6000E-01 40112 12 47 1.5500E+02 4.9800E-01 40112 12 48 1.5600E+02 3.8100E-01 2.2000E-02 40112 12 49 1.5700E+02 2.8600E-01 40112 12 50 1.5800E+02 2.0100E-01 40112 12 51 1.5900E+02 1.3700E-01 40112 12 52 1.6000E+02 9.8000E-02 40112 12 53 ENDDATA 43 40112 12 54 ENDSUBENT 3 40112 1299999 ENDENTRY 3 4011299999999 ENTRY 40193 850329 40193 0 1 SUBENT 40193001 850329 40193 1 1 BIB 11 15 40193 1 2 INSTITUTE (4CCPKUR) 40193 1 3 REFERENCE (R,YFI-16,19,7306) 40193 1 4 AUTHOR (S.M.DUBROVINA,V.I.NOVGORODTSEVA,L.N.MOROZOV, 40193 1 5 V.A.PCHELIN,L.V.CHISTJAKOV,V.A.SHIGIN,V.M.SHUBKO) 40193 1 6 TITLE THE CHANGE OF FISSION FRAGMENT-YIELD 40193 1 7 WITH NEUTRON ENERGY 40193 1 8 FACILITY NO INFORMATION 40193 1 9 INC-SOURCE NO INFORMATION 40193 1 10 METHOD THE MEASUREMENTS WERE CARRIED OUT BY 40193 1 11 RADIOCHEMICAL METHOD 40193 1 12 ANALYSIS A MASS-YIELD OF DIFFERENT FISSION-FRAGMENTS IS GIVEN 40193 1 13 RESPECTIVELY TO MASS-YIELD SR-89 40193 1 14 ERR-ANALYS THE MEASUREMENT ERROR IS EQUAL 10-20 PER-CENT 40193 1 15 STATUS DATA ARE GIVEN IN YFI-16,PAGE 19,1973 40193 1 16 HISTORY (740328C) 40193 1 17 ENDBIB 15 40193 1 18 NOCOMMON 0 0 40193 1 19 ENDSUBENT 0 40193 199999 SUBENT 40193008 850329 40193 8 1 BIB 1 1 40193 8 2 REACTION (90-TH-232(N,F),CUM,FY,,REL) 40193 8 3 ENDBIB 1 40193 8 4 COMMON 2 3 40193 8 5 EN EN-ERR 40193 8 6 MEV MEV 40193 8 7 1.3000E+01 1.5000E-01 40193 8 8 ENDCOMMON 2 3 40193 8 9 DATA 3 7 40193 8 10 ELEMENT MASS DATA 40193 8 11 NO-DIM NO-DIM ARB-UNITS 40193 8 12 3.3000E+01 7.7000E+01 7.5000E-03 40193 8 13 3.8000E+01 8.9000E+01 1.0000E+00 40193 8 14 4.2000E+01 9.9000E+01 3.5000E-01 40193 8 15 4.8000E+01 1.1500E+02 1.6000E-01 40193 8 16 5.0000E+01 1.2100E+02 1.2000E-01 40193 8 17 5.0000E+01 1.2500E+02 5.0000E-02 40193 8 18 5.6000E+01 1.4000E+02 1.2000E+00 40193 8 19 ENDDATA 9 40193 8 20 ENDSUBENT 3 40193 899999 SUBENT 40193009 850329 40193 9 1 BIB 1 1 40193 9 2 REACTION (90-TH-232(N,F),CUM,FY,,REL) 40193 9 3 ENDBIB 1 40193 9 4 COMMON 2 3 40193 9 5 EN EN-ERR 40193 9 6 MEV MEV 40193 9 7 1.5000E+01 2.5000E-01 40193 9 8 ENDCOMMON 2 3 40193 9 9 DATA 3 7 40193 9 10 ELEMENT MASS DATA 40193 9 11 NO-DIM NO-DIM ARB-UNITS 40193 9 12 3.3000E+01 7.7000E+01 7.0000E-03 40193 9 13 3.8000E+01 8.9000E+01 1.0000E+00 40193 9 14 4.2000E+01 9.9000E+01 3.6000E-01 40193 9 15 4.8000E+01 1.1500E+02 1.6000E-01 40193 9 16 5.0000E+01 1.2100E+02 1.0000E-01 40193 9 17 5.0000E+01 1.2500E+02 4.7000E-02 40193 9 18 5.6000E+01 1.4000E+02 9.0000E-01 40193 9 19 ENDDATA 9 40193 9 20 ENDSUBENT 3 40193 999999 SUBENT 40193010 850329 40193 10 1 BIB 1 1 40193 10 2 REACTION (90-TH-232(N,F),CUM,FY,,REL) 40193 10 3 ENDBIB 1 40193 10 4 COMMON 2 3 40193 10 5 EN EN-ERR 40193 10 6 MEV MEV 40193 10 7 1.7700E+01 1.5000E-01 40193 10 8 ENDCOMMON 2 3 40193 10 9 DATA 3 8 40193 10 10 ELEMENT MASS DATA 40193 10 11 NO-DIM NO-DIM ARB-UNITS 40193 10 12 3.3000E+01 7.7000E+01 9.0000E-03 40193 10 13 3.8000E+01 8.9000E+01 1.0000E+00 40193 10 14 4.2000E+01 9.9000E+01 3.7000E-01 40193 10 15 4.8000E+01 1.1500E+02 1.4000E-01 40193 10 16 5.0000E+01 1.2100E+02 1.1000E-01 40193 10 17 5.0000E+01 1.2500E+02 4.9000E-02 40193 10 18 5.1000E+01 1.2700E+02 2.2000E-02 40193 10 19 5.6000E+01 1.4000E+02 1.0000E+00 40193 10 20 ENDDATA 10 40193 10 21 ENDSUBENT 3 40193 1099999 ENDENTRY 4 4019399999999 ENTRY 40234 850329 40234 0 1 SUBENT 40234001 850329 40234 1 1 BIB 14 26 40234 1 2 INSTITUTE (4CCPFEI) 40234 1 3 REFERENCE (J,YF,7,(1),36,6807) 40234 1 4 AUTHOR (P.P.D'JACHENKO,B.D.KUZ'MINOV) 40234 1 5 TITLE NEUTRON FISSION OF U-235 AT THE EXCITATION ENERGY 40234 1 6 OF COMPOUND NUCLEUS 22 MEV. 40234 1 7 FACILITY (VDG) VAN DE GRAAFF 40234 1 8 INC-SOURCE (D-T) DEUTERON-TRITIUM REACTION 40234 1 9 METHOD (COINC) COINCIDENCE 40234 1 10 DETECTOR (SOLST) SILICON DETECTOR FOR COUNTING 40234 1 11 OF FISSION FRAGMENTS 40234 1 12 PART-DET (FF) FISSION FRAGMENTS 40234 1 13 ANALYSIS FOR DETERMINATION OF MASS-YIELD AND KINETIC ENERGY 40234 1 14 OF FISSION FRAGMENTS FOR COMPOUND NUCLEUS U-235 40234 1 15 RESULTS OF EXPERIMENTAL ARTICLE (V.I.SENCHENKO ET AL. 40234 1 16 YF,6,708,1967) WERE USED. 40234 1 17 MONITOR NO INFORMATION 40234 1 18 CORRECTION FOR DETERMINATION OF MASS-YIELD, FOLLOWING CORRECTIONS 40234 1 19 WERE TAKEN INTO ACCOUNT 40234 1 20 1. SHEPPARD CORRECTION 40234 1 21 2. CORRECTION CONNECTED WITH IRRADIATION OF DETECTORS 40234 1 22 BY PROMPT NEUTRONS 40234 1 23 3. GEOMETRY EFFICIENCY OF COUNTING OF FISSION 40234 1 24 FRAGMENT IS EQUAL 30 PER-CENT 40234 1 25 ERR-ANALYS ERROR OF MEASUREMENT IS DETERMINED IN THE MAIN 40234 1 26 BY STATISTICAL ERROR 40234 1 27 HISTORY (741224C) 40234 1 28 ENDBIB 26 40234 1 29 NOCOMMON 0 0 40234 1 30 ENDSUBENT 0 40234 199999 SUBENT 40234002 850329 40234 2 1 BIB 1 1 40234 2 2 REACTION (92-U-235(N,F),PRE,FY) 40234 2 3 ENDBIB 1 40234 2 4 COMMON 1 3 40234 2 5 EN 40234 2 6 MEV 40234 2 7 1.5500E+01 40234 2 8 ENDCOMMON 1 3 40234 2 9 DATA 3 39 40234 2 10 MASS DATA DATA-ERR 40234 2 11 NO-DIM PC/FIS PC/FIS 40234 2 12 1.1800E+02 1.1000E+00 3.0000E-01 40234 2 13 1.1900E+02 1.1000E+00 3.0000E-01 40234 2 14 1.2000E+02 1.1000E+00 3.0000E-01 40234 2 15 1.2100E+02 1.0000E+00 3.0000E-01 40234 2 16 1.2200E+02 1.0000E+00 1.9000E+00 40234 2 17 1.2300E+02 1.2000E+00 2.1000E+00 40234 2 18 1.2400E+02 1.3000E+00 2.3000E+00 40234 2 19 1.2500E+02 1.4000E+00 2.4000E+00 40234 2 20 1.2600E+02 1.6000E+00 2.7000E+00 40234 2 21 1.2700E+02 1.8000E+00 2.9000E+00 40234 2 22 1.2800E+02 2.1000E+00 3.2000E+00 40234 2 23 1.2900E+02 2.4000E+00 3.1000E+00 40234 2 24 1.3000E+02 2.9000E+00 3.4000E+00 40234 2 25 1.3100E+02 3.3000E+00 3.6000E+00 40234 2 26 1.3200E+02 3.7000E+00 3.7000E+00 40234 2 27 1.3300E+02 4.2000E+00 4.0000E+00 40234 2 28 1.3400E+02 4.4000E+00 3.8000E+00 40234 2 29 1.3500E+02 4.7000E+00 4.1000E+00 40234 2 30 1.3600E+02 4.8000E+00 4.0000E+00 40234 2 31 1.3700E+02 5.0000E+00 4.0000E+00 40234 2 32 1.3800E+02 5.2000E+00 4.1000E+00 40234 2 33 1.3900E+02 5.3000E+00 4.0000E+00 40234 2 34 1.4000E+02 5.2000E+00 3.8000E+00 40234 2 35 1.4100E+02 5.0000E+00 3.7000E+00 40234 2 36 1.4200E+02 4.7000E+00 3.4000E+00 40234 2 37 1.4300E+02 4.3000E+00 3.2000E+00 40234 2 38 1.4400E+02 3.8000E+00 2.8000E+00 40234 2 39 1.4500E+02 3.4000E+00 2.5000E+00 40234 2 40 1.4600E+02 3.0000E+00 2.4000E+00 40234 2 41 1.4700E+02 2.5000E+00 2.2000E+00 40234 2 42 1.4800E+02 2.0000E+00 1.9000E+00 40234 2 43 1.4900E+02 1.6000E+00 1.6000E+00 40234 2 44 1.5000E+02 1.3000E+00 1.4000E+00 40234 2 45 1.5100E+02 1.0000E+00 1.0000E+00 40234 2 46 1.5200E+02 7.0000E-01 7.0000E-01 40234 2 47 1.5300E+02 4.0000E-01 4.0000E-01 40234 2 48 1.5400E+02 3.0000E-01 3.0000E-01 40234 2 49 1.5500E+02 2.0000E-01 3.0000E-01 40234 2 50 1.5600E+02 1.0000E-01 3.0000E-01 40234 2 51 ENDDATA 41 40234 2 52 ENDSUBENT 3 40234 299999 ENDENTRY 2 4023499999999 ENTRY 40235 850329 40235 0 1 SUBENT 40235001 850329 40235 1 1 BIB 14 33 40235 1 2 INSTITUTE (4CCPFEI) 40235 1 3 REFERENCE (J,YF,8,(2),286,6808) 40235 1 4 (R,ICD-4,346,67) DATA GIVEN 40235 1 5 AUTHOR (P.P.D'JACHENKO,B.D.KUZ'MINOV,M.Z.TARASKO) 40235 1 6 TITLE ENERGY AND MASS DISTRIBUTION OF FRAGMENTS 40235 1 7 AT THE FISSION OF U-235 BY MONOENERGETIC NEUTRONS 40235 1 8 IN THE ENERGY INTERVAL 0-15.5 MEV 40235 1 9 FACILITY (VDG) VAN DE GRAAFF 40235 1 10 INC-SOURCE (P-T) PROTON-TRITIUM REACTION FOR NEUTRON ENERGY 40235 1 11 INTERVAL 0.28-3.5 MEV 40235 1 12 (D-D) - FOR NEUTRON ENERGY INTERVAL 5-7 MEV 40235 1 13 (D-T) - FOR EN=15.5 MEV 40235 1 14 METHOD (COINC) COINCIDENCE 40235 1 15 DETECTOR (SOLST) SILICON DETECTOR FOR COUNTING 40235 1 16 OF FISSION FRAGMENTS 40235 1 17 PART-DET (FF) FISSION FRAGMENTS 40235 1 18 ANALYSIS FOR DETERMINATION OF MASS-YIELD AND KINETIC ENERGY 40235 1 19 OF FISSION FRAGMENT FOR COMPOUND NUCLEUS U-235 40235 1 20 RESULTS OF FOLLOWING ARTICLES WERE USED- 40235 1 21 1.G.P.FORD,R.B.LEACHMAN,PHYS.REV.,137,B826,1965 40235 1 22 2. V.M.PANKRATOV,V.M.STRUTINSKIJ,AE,14,171,1963 40235 1 23 3. V.I.SENCHENKO ET AL. YF,5,514,1967 40235 1 24 MONITOR NO INFORMATION 40235 1 25 CORRECTION FOLLOWING CORRECTIONS WERE TAKEN INTO ACCOUNT 40235 1 26 1. SHEPPARD CORRECTION 40235 1 27 2. CORRECTION CONNECTED WITH IRRADIATION OF DETECTOR 40235 1 28 BY PROMPT NEUTRONS 40235 1 29 3. ON MOTION OF CENTRE-OF-MASS 40235 1 30 4. GEOMETRY EFFICIENCY OF COUNTING FISSION 40235 1 31 FRAGMENTS BY DETECTORS IS EQUAL 30 PER-CENT. 40235 1 32 ERR-ANALYS ERROR OF MEASUREMENTS IS DETERMINED IN THE MAIN 40235 1 33 BY STATISTICAL ERROR 40235 1 34 HISTORY (741217C) 40235 1 35 ENDBIB 33 40235 1 36 NOCOMMON 0 0 40235 1 37 ENDSUBENT 0 40235 199999 SUBENT 40235016 850329 40235 16 1 BIB 1 1 40235 16 2 REACTION (92-U-235(N,F),PRE,FY) 40235 16 3 ENDBIB 1 40235 16 4 COMMON 2 3 40235 16 5 EN EN-ERR 40235 16 6 MEV MEV 40235 16 7 1.5500E+01 1.0000E+00 40235 16 8 ENDCOMMON 2 3 40235 16 9 DATA 2 40 40235 16 10 MASS DATA 40235 16 11 NO-DIM PC/FIS 40235 16 12 1.1800E+02 2.0500E+00 40235 16 13 1.1900E+02 2.0300E+00 40235 16 14 1.2000E+02 2.0400E+00 40235 16 15 1.2100E+02 1.8400E+00 40235 16 16 1.2200E+02 1.7700E+00 40235 16 17 1.2300E+02 1.9300E+00 40235 16 18 1.2400E+02 2.0600E+00 40235 16 19 1.2500E+02 2.1700E+00 40235 16 20 1.2600E+02 2.8300E+00 40235 16 21 1.2700E+02 3.3700E+00 40235 16 22 1.2800E+02 3.8600E+00 40235 16 23 1.2900E+02 4.3600E+00 40235 16 24 1.3000E+02 4.1700E+00 40235 16 25 1.3100E+02 4.2600E+00 40235 16 26 1.3200E+02 4.0100E+00 40235 16 27 1.3300E+02 3.9400E+00 40235 16 28 1.3400E+02 3.9800E+00 40235 16 29 1.3500E+02 3.9000E+00 40235 16 30 1.3600E+02 3.9300E+00 40235 16 31 1.3700E+02 3.7400E+00 40235 16 32 1.3800E+02 3.6700E+00 40235 16 33 1.3900E+02 3.6800E+00 40235 16 34 1.4000E+02 3.4100E+00 40235 16 35 1.4100E+02 3.3600E+00 40235 16 36 1.4200E+02 3.1400E+00 40235 16 37 1.4300E+02 2.8300E+00 40235 16 38 1.4400E+02 3.1800E+00 40235 16 39 1.4500E+02 2.2000E+00 40235 16 40 1.4600E+02 2.2300E+00 40235 16 41 1.4700E+02 2.2200E+00 40235 16 42 1.4800E+02 1.9300E+00 40235 16 43 1.4900E+02 1.7100E+00 40235 16 44 1.5000E+02 1.4600E+00 40235 16 45 1.5100E+02 9.8000E-01 40235 16 46 1.5200E+02 6.0000E-01 40235 16 47 1.5300E+02 4.0000E-01 40235 16 48 1.5400E+02 3.5000E-01 40235 16 49 1.5500E+02 1.4000E-01 40235 16 50 1.5600E+02 1.8000E-01 40235 16 51 1.5700E+02 8.0000E-02 40235 16 52 ENDDATA 42 40235 16 53 ENDSUBENT 2 40235 1699999 ENDENTRY 2 4023599999999 ENTRY 40329 980401 40329 0 1 SUBENT 40329001 980401 40329 1 1 BIB 11 21 40329 1 2 INSTITUTE (4RUSKUR) 40329 1 3 REFERENCE (J,YF,6,(3),454,6709) IN RUSSIAN. MAIN REFERENCE 40329 1 4 DATA ARE GIVEN 40329 1 5 (J,SNP,6,331,6803) ENGLISH TRANSLATION OF YF 6 454 40329 1 6 AUTHOR (N.I.BORISOVA,S.M.DUBROVINA,V.I.NOVGORODTSEVA, 40329 1 7 V.A.PCHELIN,V.A.SHIGIN,V.M.SHUBKO) 40329 1 8 TITLE VARIATION OF MASS DISTRIBUTIONS OF U-238 FISSION 40329 1 9 FRAGMENTS WITH NEUTRON ENERGY 40329 1 10 FACILITY (VDG) ELECTROSTATIC ACCELERATOR 40329 1 11 INC-SOURCE (P-T,D-D,D-T) 40329 1 12 METHOD (RCHEM) 40329 1 13 MONITOR NO INFORMATION 40329 1 14 ERR-ANALYS (ERR-T) TOTAL ERRORS ARE GIVEN 40329 1 15 STATUS (TABLE) DATA ARE TAKEN FROM THE TABLE 1 40329 1 16 OF MAIN REFERENCE 40329 1 17 HISTORY (920508C) + + COMPILED AT THE CENTRE - CJD + + 40329 1 18 (920911A) DATA IN SAN 003, SAN 004 CORRECTED 40329 1 19 (930614U) .CORRECTIONS MADE AT NNDC 40329 1 20 (980401U) .FINAL CORRECTIONS MADE AT CJD - INSTITUTE 40329 1 21 AND REFERENCE CODES CORRECTED 40329 1 22 .ALTER FLAGS ADDED 40329 1 23 ENDBIB 21 40329 1 24 NOCOMMON 0 0 40329 1 25 ENDSUBENT 0 40329 199999 SUBENT 40329002 920512 40329 2 1 BIB 1 2 40329 2 2 REACTION ((92-U-238(N,F)42-MO-99,CUM,FY)/ 40329 2 3 (92-U-238(N,F)56-BA-140,CUM,FY)) 40329 2 4 ENDBIB 2 40329 2 5 NOCOMMON 0 0 40329 2 6 DATA 4 4 40329 2 7 EN EN-RSL DATA ERR-T 40329 2 8 MEV MEV NO-DIM PER-CENT 40329 2 9 13.0 0.15 1.16 10. 40329 2 10 15.0 0.25 1.22 10. 40329 2 11 16.4 0.25 1.22 10. 40329 2 12 17.7 0.15 1.29 10. 40329 2 13 ENDDATA 6 40329 2 14 ENDSUBENT 4 40329 299999 SUBENT 40329003 980401 40329 3 1 BIB 2 6 40329 3 2 REACTION ((92-U-238(N,F)ELEM/MASS,CUM,FY,,FCT)/ 40329 3 3 ((92-U-238(N,F)42-MO-99,CUM,FY)+ 40329 3 4 (92-U-238(N,F)56-BA-140,CUM,FY))) FIGURES IN DATA SECT.40329 3 5 ARE MULTIPLIED BY TWO 40329 3 6 HISTORY (930614U) .'FCT' ADDED TO REACTION SF8 40329 3 7 (980401U) .18 DATA VALUES CORRECTED 40329 3 8 ENDBIB 6 40329 3 9 NOCOMMON 0 0 40329 3 10 DATA 6 12 40329 3 11 EN EN-RSL ELEMENT MASS DATA ERR-T 40329 3 12 MEV MEV NO-DIM NO-DIM NO-DIM PER-CENT 40329 3 13 13.0 0.15 33. 77. 4.90196E-03 10. 40329 3 14 13.0 0.15 47. 111. 1.42857E-01 10. 40329 3 15 13.0 0.15 48. 115. 1.13636E-01 10. 40329 3 16 15.0 0.25 33. 77. 6.41025E-03 10. 40329 3 17 15.0 0.25 47. 111. 1.69491E-01 10. 40329 3 18 15.0 0.25 48. 115. 1.53846E-01 10. 40329 3 19 16.4 0.25 33. 77. 6.89655E-03 10. 40329 3 20 16.4 0.25 47. 111. 1.88679E-01 10. 40329 3 21 16.4 0.25 48. 115. 1.72413E-01 10. 40329 3 22 17.7 0.15 33. 77. 6.25000E-03 10. 40329 3 23 17.7 0.15 47. 111. 1.58730E-01 10. 40329 3 24 17.7 0.15 48. 115. 1.47058E-01 10. 40329 3 25 ENDDATA 14 40329 3 26 ENDSUBENT 6 40329 399999 SUBENT 40329004 980401 40329 4 1 BIB 3 8 40329 4 2 REACTION ((92-U-238(N,F)ELEM/MASS,CUM,FY)/ 40329 4 3 (92-U-238(N,F)42-MO-99,CUM,FY)) 40329 4 4 STATUS (DEP,40329002) 40329 4 5 (DEP,40329003) RECALCULATED BY COMPILER USING 40329 4 6 EXPRESSION YIELD(IN DATA SECTION) = 40329 4 7 YIELD(IN ARTICLE) * (Y(BA-140)/Y(MO-99)+1)/240329 4 8 HISTORY (930614A) .STATUS CODE CHANGED TO 'DEP' 40329 4 9 (980401A) .DATA VALUES ARE RECALCULATED 40329 4 10 ENDBIB 8 40329 4 11 NOCOMMON 0 0 40329 4 12 DATA 6 12 40329 4 13 EN EN-RSL ELEMENT MASS DATA ERR-T 40329 4 14 MEV MEV NO-DIM NO-DIM NO-DIM PER-CENT 40329 4 15 13.0 0.15 33. 77. 4.56389E-03 10. 40329 4 16 13.0 0.15 47. 111. .133004 10. 40329 4 17 13.0 0.15 48. 115. .105799 10. 40329 4 18 15.0 0.25 33. 77. 5.83228E-03 10. 40329 4 19 15.0 0.25 47. 111. .154209 10. 40329 4 20 15.0 0.25 48. 115. .139974 10. 40329 4 21 16.4 0.25 33. 77. 6.27473E-03 10. 40329 4 22 16.4 0.25 47. 111. .171667 10. 40329 4 23 16.4 0.25 48. 115. .156868 10. 40329 4 24 17.7 0.15 33. 77. 5.54748E-03 10. 40329 4 25 17.7 0.15 47. 111. .140888 10. 40329 4 26 17.7 0.15 48. 115. .130528 10. 40329 4 27 ENDDATA 14 40329 4 28 ENDSUBENT 6 40329 499999 ENDENTRY 4 4032999999999 ENTRY 40422 920519 40422 0 1 SUBENT 40422001 920519 40422 1 1 BIB 10 16 40422 1 2 INSTITUTE (4CCPRI ) 40422 1 3 REFERENCE (J,YF,11,(6),1178,7006) 40422 1 4 (J,SNP,11,654,7012) ENGLISH TRANSLATION 40422 1 5 AUTHOR (K.A.PETRZHAK,V.F.TEPLYKH,M.G.PAN'YAN) 40422 1 6 TITLE MASS-SPECTROMETRIC DETERMINATION OF XE-ISOTOPE 40422 1 7 RELATIVE YIELDS FROM NATURAL URANIUM FISSION BY 14.7 40422 1 8 MEV NEUTRONS 40422 1 9 FACILITY (VDG) 40422 1 10 INC-SOURCE (D-T) 40422 1 11 SAMPLE DISK MADE OF EUTECTICAL ALLOY OF NATURAL URANIUM 40422 1 12 WITH NICKEL. DIAMETER 10 MM, MASS 4.2 GRAM, 40422 1 13 WRAPPED UP IN CADMIUM FOIL 0.5 MM THICKNESS 40422 1 14 METHOD (ASEP) 40422 1 15 STATUS DATA ARE TAKEN FROM THE REFERENCE-ONE 40422 1 16 HISTORY (920518C) + + COMPILED AT THE CENTRE - CJD + + 40422 1 17 (930217U) DATA UNITS CORRECTED IN SAN 002, 003 40422 1 18 ENDBIB 16 40422 1 19 NOCOMMON 0 0 40422 1 20 ENDSUBENT 0 40422 199999 SUBENT 40422002 930217 40422 2 1 BIB 4 7 40422 2 2 REACTION ((92-U-238(N,F)ELEM/MASS,CUM,FY)/ 40422 2 3 (92-U-238(N,F)ELEM,CUM,FY)) 40422 2 4 MONITOR ABSOLUTE MEASUREMENTS 40422 2 5 ERR-ANALYS (DATA-ERR) ERRORS ARE NOT SPECIFIED. CALCULATED 40422 2 6 BY COMPILER ACCORDIND TO EXPRESSION 40422 2 7 SQRT((ERR1)**2 + (ERR2)**2) 40422 2 8 HISTORY (930217U) DATA UNITS CORRECTED 40422 2 9 ENDBIB 7 40422 2 10 COMMON 1 3 40422 2 11 EN 40422 2 12 MEV 40422 2 13 14.7 40422 2 14 ENDCOMMON 1 3 40422 2 15 DATA 4 4 40422 2 16 ELEMENT MASS DATA DATA-ERR 40422 2 17 NO-DIM NO-DIM NO-DIM NO-DIM 40422 2 18 54. 131. 18.64 .77 40422 2 19 54. 132. 23.06 .71 40422 2 20 54. 134. 31.62 .68 40422 2 21 54. 136. 26.62 .81 40422 2 22 ENDDATA 6 40422 2 23 ENDSUBENT 4 40422 299999 SUBENT 40422003 930217 40422 3 1 BIB 5 6 40422 3 2 REACTION ((92-U-238(N,F)ELEM/MASS,CUM,FY)/ 40422 3 3 (92-U-238(N,F)ELEM,CUM,FY)) 40422 3 4 MONITOR (92-U-238(N,F)52-TE-132,CUM,FY) 40422 3 5 MONIT-REF (,K.M.BROOM,J,PR,126,672,62) 40422 3 6 ERR-ANALYS (DATA-ERR) ERRORS ARE NOT SPECIFIED. 40422 3 7 HISTORY (930217U) DATA UNITS CHANGED 40422 3 8 ENDBIB 6 40422 3 9 COMMON 1 3 40422 3 10 MONIT 40422 3 11 PC/FIS 40422 3 12 4.7 40422 3 13 ENDCOMMON 1 3 40422 3 14 DATA 5 4 40422 3 15 EN ELEMENT MASS DATA DATA-ERR 40422 3 16 MEV NO-DIM NO-DIM NO-DIM NO-DIM 40422 3 17 18.9 54. 131. 3.81 0.10 40422 3 18 18.9 54. 132. 4.7 0.10 40422 3 19 18.9 54. 134. 6.46 0.10 40422 3 20 18.9 54. 136. 5.43 0.11 40422 3 21 ENDDATA 6 40422 3 22 ENDSUBENT 5 40422 399999 ENDENTRY 3 4042299999999 ENTRY 40428 850423 40428 0 1 SUBENT 40428001 850423 40428 1 1 BIB 10 18 40428 1 2 INSTITUTE (4CCPKUR) 40428 1 3 REFERENCE (J,YF,24,(6),1089,7612) 40428 1 4 (P,YFI-24,8,7706) 40428 1 5 AUTHOR (S.K.LISIN,L.N.MOROZOV,V.A.PCHELIN,L,V.CHISTJAKOV, 40428 1 6 V.A.SHIGIN,V.M.SHUBKO) 40428 1 7 TITLE BARRIERS OF EMITTED FRAGMENTS AT FISSION OF TH-232 BY 40428 1 8 NEUTRONS 40428 1 9 FACILITY (VDG) ELECTROSTATIC ACCELERATOR 40428 1 10 INC-SOURCE (P-T) NEUTRONS WITH EN LESS 2.MEV 40428 1 11 (D-D) NEUTRONS WITH EN EQUAL OR MORE 2.MEV 40428 1 12 METHOD (CHSEP) 40428 1 13 CORRECTION FOR EN LESS 2.MEV RESOLUTION IS 50.KEV, FOR EN EQUAL 40428 1 14 OR MORE 2.MEV RESOLUTION IS 100.KEV 40428 1 15 ERR-ANALYS (ERR-1) ERROR FOR FY LESS THAN 1.E-4 OF MOST PROBA-40428 1 16 BLF FISSION AND FOR FY OF SIMMETRIC FISSION 40428 1 17 (ERR-2) ERROR FOR FY FOR OTHER CASES 40428 1 18 HISTORY (791025C) 40428 1 19 (840210A) SOME MINOR ERRORS AND ERR-1, ERR-2 CORRECTED 40428 1 20 ENDBIB 18 40428 1 21 COMMON 2 3 40428 1 22 ERR-1 ERR-2 40428 1 23 PER-CENT PER-CENT 40428 1 24 3.0000E+01 1.0000E+01 40428 1 25 ENDCOMMON 2 3 40428 1 26 ENDSUBENT 2 40428 199999 SUBENT 40428002 791025 40428 2 1 BIB 1 2 40428 2 2 REACTION (90-TH-232(N,F)ELEM/MASS,CUM,FY,,REL) FY ARE GIVEN 40428 2 3 RELATIVLY YIELD OF SR-89 40428 2 4 ENDBIB 2 40428 2 5 NOCOMMON 0 0 40428 2 6 DATA 4 11 40428 2 7 EN ELEMENT MASS DATA 40428 2 8 MEV NO-DIM NO-DIM ARB-UNITS 40428 2 9 1.3000E+01 3.3000E+01 7.7000E+01 7.5000E-03 40428 2 10 1.3000E+01 3.8000E+01 8.9000E+01 1.0000E+00 40428 2 11 1.3000E+01 4.2000E+01 9.9000E+01 3.5000E-01 40428 2 12 1.3000E+01 4.8000E+01 1.1500E+02 1.6000E-01 40428 2 13 1.3000E+01 5.0000E+01 1.2100E+02 1.2000E-01 40428 2 14 1.3000E+01 5.0000E+01 1.2500E+02 5.0000E-02 40428 2 15 1.3000E+01 5.1000E+01 1.2700E+02 0.0000E+00 40428 2 16 1.3000E+01 5.1000E+01 1.2900E+02 0.0000E+00 40428 2 17 1.3000E+01 5.6000E+01 1.4000E+02 1.2000E+00 40428 2 18 1.3000E+01 5.8000E+01 1.4100E+02 0.0000E+00 40428 2 19 1.3000E+01 5.8000E+01 1.4400E+02 0.0000E+00 40428 2 20 ENDDATA 13 40428 2 21 ENDSUBENT 4 40428 299999 ENDENTRY 2 4042899999999 ENTRY 40545 920809 40545 0 1 SUBENT 40545001 920809 40545 1 1 BIB 9 17 40545 1 2 INSTITUTE (4CCPTIL,4CCPRI ) 40545 1 3 REFERENCE (J,YF,29,(2),293,7902) 40545 1 4 AUTHOR (V.F.TEPLYKH,E.V.PLATYGINA,K.A.PETRZHAK, 40545 1 5 B.M.MARKOV,V.I.KOZINETS) 40545 1 6 TITLE FINE STRUCTURE IN MASS YIELDS OF NEUTRON-INDUCED 40545 1 7 FISSION PRODUCTS OF NP-237 40545 1 8 METHOD (ASEP) 40545 1 9 MONITOR RELATIVE MEASUREMENTS 40545 1 10 ERR-ANALYS ERRORS NOT SPECIFIED 40545 1 11 STATUS THIS ENTRY COINCIDES WITH THAT OF RIDER'S 90751 40545 1 12 RIDER'S REFERENCE 79TEP1 40545 1 13 HISTORY (800901C) COMPILED AT THE CENTRE 40545 1 14 (850927A) NEW SUBENT 003 ADDED 40545 1 15 (911206U) CONNECTION WITH RIDER'S ENTRY 90751 IS 40545 1 16 ESTABLISHED. 40545 1 17 (920809U) 'METHOD' KEYWORD ADDED AND 'REL' MODIFIER 40545 1 18 EXPLAINED 40545 1 19 ENDBIB 17 40545 1 20 NOCOMMON 0 0 40545 1 21 ENDSUBENT 0 40545 199999 SUBENT 40545002 920809 40545 2 1 BIB 3 4 40545 2 2 REACTION (93-NP-237(N,F)ELEM/MASS,CUM,FY,,REL) SUM OF RELATIVE 40545 2 3 YIELDS FOR GIVEN ELEMENT = 100 % 40545 2 4 FACILITY (VDG,4CCPTIL) 'NG-200'-NEUTRON GENERATOR 40545 2 5 HISTORY (920809U) 'REL' MODIFIER EXPLAINED 40545 2 6 ENDBIB 4 40545 2 7 COMMON 2 3 40545 2 8 EN ELEMENT 40545 2 9 MEV NO-DIM 40545 2 10 14.7 54. 40545 2 11 ENDCOMMON 2 3 40545 2 12 DATA 3 4 40545 2 13 MASS DATA DATA-ERR 40545 2 14 NO-DIM ARB-UNITS ARB-UNITS 40545 2 15 131. 21.79 0.16 40545 2 16 132. 23.30 0.14 40545 2 17 134. 28.93 0.18 40545 2 18 136. 25.96 0.20 40545 2 19 ENDDATA 6 40545 2 20 ENDSUBENT 3 40545 299999 ENDENTRY 2 4054599999999 ENTRY 41060 960612 41060 0 1 SUBENT 41060001 960612 41060 1 1 BIB 15 20 41060 1 2 INSTITUTE (4RUSFEI) 41060 1 3 REFERENCE (W,GOVERDOVSKIY,9209) 41060 1 4 AUTHOR (A.A.GOVERDOVSKIY,V.F.MITROFANOV) 41060 1 5 TITLE AMERITIUM FISSION-FRAGMENTS YIELD 41060 1 6 FACILITY (VDG) ACCELERATOR CG-2.5 IPPE) 41060 1 7 INC-SOURCE (D-T) NEUTRON SOURCE- T(D,N)-REACTION 41060 1 8 SAMPLE THIN AM,U-TARGETS 41060 1 9 0.05-0.09 MG/CM2, AL2-O3 BACKING: 0.04 MG/CM2 41060 1 10 METHOD 2E-METHOD 41060 1 11 DETECTOR SI-AU-DETECTORS 41060 1 12 MONITOR (92-U-235(N,F),PRE,FY) N=THERMAL 41060 1 13 CORRECTION PROMPT NEUTRON EMISSION-CORRECTIONS 41060 1 14 ERR-ANALYS (ERR-S) ONE-SIGMA STATISTICAL ERROR 41060 1 15 COMMENT MASS SPECTRUM FOR FISSILE SYSTEM AM-244 41060 1 16 CORRECTED ON IMPURITY OF (N,N'F) AND (N,2N'F) 41060 1 17 REACTIONS) 41060 1 18 STATUS (APRVD) DATA ARE OBTAINED FROM THE AUTHOR 41060 1 19 GOVERDOVSKIY, 920922 41060 1 20 HISTORY (940330C) + + COMPILED AT THE CENTRE - CJD + + 41060 1 21 (960612U) + + REFERENCE ADDED IN SAN OO2 41060 1 22 ENDBIB 20 41060 1 23 COMMON 2 3 41060 1 24 EN EN-NRM 41060 1 25 MEV EV 41060 1 26 16.5 2.53E-02 41060 1 27 ENDCOMMON 2 3 41060 1 28 ENDSUBENT 2 41060 199999 SUBENT 41060002 960612 41060 2 1 BIB 2 2 41060 2 2 REFERENCE (J,YF,58,(11),1948,9511) GRAPH IS GIVEN 41060 2 3 REACTION (95-AM-243(N,F)MASS,PRE,FY) 41060 2 4 ENDBIB 2 41060 2 5 NOCOMMON 0 0 41060 2 6 DATA 3 45 41060 2 7 MASS DATA ERR-S 41060 2 8 NO-DIM PC/FIS PC/FIS 41060 2 9 122. 1.91 .15 41060 2 10 123. 1.86 .15 41060 2 11 124. 1.80 .15 41060 2 12 125. 1.86 .15 41060 2 13 126. 1.90 .15 41060 2 14 127. 2.05 .16 41060 2 15 128. 2.25 .16 41060 2 16 129. 2.55 .17 41060 2 17 130. 3.14 .19 41060 2 18 131. 3.70 .21 41060 2 19 132. 4.22 .22 41060 2 20 133. 4.34 .23 41060 2 21 134. 4.36 .23 41060 2 22 135. 4.36 .23 41060 2 23 136. 4.37 .23 41060 2 24 137. 4.26 .22 41060 2 25 138. 4.20 .22 41060 2 26 139. 4.14 .22 41060 2 27 140. 4.10 .22 41060 2 28 141. 4.00 .22 41060 2 29 142. 3.90 .21 41060 2 30 143. 3.72 .21 41060 2 31 144. 3.45 .20 41060 2 32 145. 3.30 .20 41060 2 33 146. 3.00 .19 41060 2 34 147. 2.62 .18 41060 2 35 148. 2.40 .17 41060 2 36 149. 2.24 .16 41060 2 37 150. 2.00 .15 41060 2 38 151. 1.80 .15 41060 2 39 152. 1.58 .14 41060 2 40 153. 1.35 .13 41060 2 41 154. 1.14 .12 41060 2 42 155. .94 .11 41060 2 43 156. .80 .10 41060 2 44 157. .60 .08 41060 2 45 158. .50 .08 41060 2 46 159. .38 .07 41060 2 47 160. .30 .06 41060 2 48 161. .24 .05 41060 2 49 162. .18 .05 41060 2 50 163. .14 .04 41060 2 51 164. .09 .03 41060 2 52 165. .05 .02 41060 2 53 166. .02 .02 41060 2 54 ENDDATA 47 41060 2 55 ENDSUBENT 3 41060 299999 SUBENT 41060003 940331 41060 3 1 BIB 1 1 41060 3 2 REACTION (95-AM-244(N,F)MASS,PRE,FY) 41060 3 3 ENDBIB 1 41060 3 4 NOCOMMON 0 0 41060 3 5 DATA 3 45 41060 3 6 MASS DATA ERR-S 41060 3 7 NO-DIM PC/FIS PC/FIS 41060 3 8 122. 3.12 .19 41060 3 9 123. 3.09 .19 41060 3 10 124. 2.99 .19 41060 3 11 125. 2.88 .18 41060 3 12 126. 2.68 .18 41060 3 13 127. 2.60 .17 41060 3 14 128. 2.68 .18 41060 3 15 129. 2.78 .18 41060 3 16 130. 3.27 .20 41060 3 17 131. 3.88 .21 41060 3 18 132. 3.92 .21 41060 3 19 133. 3.89 .21 41060 3 20 134. 3.73 .21 41060 3 21 135. 3.60 .21 41060 3 22 136. 3.48 .20 41060 3 23 137. 3.35 .20 41060 3 24 138. 3.24 .20 41060 3 25 139. 3.19 .19 41060 3 26 140. 3.09 .19 41060 3 27 141. 3.07 .19 41060 3 28 142. 2.98 .19 41060 3 29 143. 2.94 .19 41060 3 30 144. 2.91 .19 41060 3 31 145. 2.86 .18 41060 3 32 146. 2.78 .18 41060 3 33 147. 2.62 .18 41060 3 34 148. 2.50 .17 41060 3 35 149. 2.31 .16 41060 3 36 150. 2.13 .16 41060 3 37 151. 1.96 .15 41060 3 38 152. 1.80 .15 41060 3 39 153. 1.55 .14 41060 3 40 154. 1.37 .13 41060 3 41 155. 1.18 .12 41060 3 42 156. .98 .11 41060 3 43 157. .82 .10 41060 3 44 158. .65 .09 41060 3 45 159. .57 .08 41060 3 46 160. .47 .07 41060 3 47 161. .36 .07 41060 3 48 162. .29 .06 41060 3 49 163. .20 .05 41060 3 50 164. .13 .04 41060 3 51 165. .08 .03 41060 3 52 166. .03 .02 41060 3 53 ENDDATA 47 41060 3 54 ENDSUBENT 3 41060 399999 ENDENTRY 3 4106099999999 ENTRY 41069 911217 41069 0 1 SUBENT 41069001 911217 41069 1 1 BIB 9 11 41069 1 2 INSTITUTE (4CCPKUR) 41069 1 3 REFERENCE (J,YF,6,454,68) 41069 1 4 (J,SNP,6,331,68) ENGLISH TRANSLATION 41069 1 5 AUTHOR (N.I.BORISOVA,S.M.DUBROVINA) 41069 1 6 TITLE VARIATION OF MASS DISTRIBUTION OF 238U FISSION 41069 1 7 FRAGMENTS WITH NEUTRON ENERGY 41069 1 8 METHOD (RCHEM) 41069 1 9 MONITOR NO INFORMATION 41069 1 10 ERR-ANALYS ERRORS ARE NOT SPECIFIED 41069 1 11 STATUS (RIDER) RIDER'S REFERENCE 68BOR2 41069 1 12 HISTORY (911217T) CONVERTED FROM RIDER'S ENTRY 90345 41069 1 13 ENDBIB 11 41069 1 14 NOCOMMON 0 0 41069 1 15 ENDSUBENT 0 41069 199999 SUBENT 41069002 911217 41069 2 1 BIB 1 2 41069 2 2 REACTION ((92-U-238(N,F)ELEM/MASS,CUM,FY)/ 41069 2 3 (92-U-238(N,F)42-MO-99,CUM,FY)) 41069 2 4 ENDBIB 2 41069 2 5 NOCOMMON 0 0 41069 2 6 DATA 5 9 41069 2 7 EN ELEMENT MASS ISOMER DATA 41069 2 8 MEV NO-DIM NO-DIM NO-DIM NO-DIM 41069 2 9 13. 33. 77. .00456 41069 2 10 13. 47. 111. 0. .133 41069 2 11 13. 48. 115. 0. .106 41069 2 12 16. 33. 77. .00627 41069 2 13 16. 47. 111. 0. .172 41069 2 14 16. 48. 115. 0. .157 41069 2 15 18. 33. 77. .00555 41069 2 16 18. 47. 111. 0. .141 41069 2 17 18. 48. 115. 0. .131 41069 2 18 ENDDATA 11 41069 2 19 ENDSUBENT 5 41069 299999 ENDENTRY 2 4106999999999 ENTRY 41070 920811 41070 0 1 SUBENT 41070001 920811 41070 1 1 BIB 9 14 41070 1 2 INSTITUTE (4CCPKUR) 41070 1 3 REFERENCE (J,AE,10,(1),13,61) 41070 1 4 (J,SJA,10,10,61) ENGLISH TRANSLATION OF AE,10,13,61 41070 1 5 AEC-TR-4682 IS ANOTHER ENGLISH TRANSLATION 41070 1 6 AUTHOR (E.K.BONYUSHKIN,YU.S.ZAMYATNIN,V.V.SPEKTOR, 41070 1 7 V.V.RACHEV,V.R.NEGINA,V.N.ZAMYATNINA) 41070 1 8 TITLE FRAGMENT YIELD IN THE FISSION OF U-233 AND PU-239 41070 1 9 BY FAST NEUTRONS 41070 1 10 METHOD (RCHEM) 41070 1 11 MONITOR ABSOLUTE MEASUREMENTS 41070 1 12 ERR-ANALYS ERRORS ARE NOT SPECIFIED 41070 1 13 STATUS (RIDER) RIDER'S REFERENCE 61BON1 41070 1 14 HISTORY (911105T) CONVERTED FROM RIDER'S ENTRY 90201 41070 1 15 (920811U) ONE DATA LINE CHANGED TO MONITOR IN SAN 004 41070 1 16 ENDBIB 14 41070 1 17 NOCOMMON 0 0 41070 1 18 ENDSUBENT 0 41070 199999 SUBENT 41070002 911105 41070 2 1 BIB 4 4 41070 2 2 REACTION (94-PU-239(N,F)ELEM/MASS,CUM,FY) 41070 2 3 FACILITY (VDG) ACCELERATING TUBE, DEYTON ENERGY 150 KEV 41070 2 4 INC-SOURCE (D-T) 41070 2 5 MONITOR (94-PU-239(N,F)56-BA-140,CUM,FY) 41070 2 6 ENDBIB 4 41070 2 7 COMMON 1 3 41070 2 8 EN 41070 2 9 EV 41070 2 10 14. E+06 41070 2 11 ENDCOMMON 1 3 41070 2 12 DATA 6 8 41070 2 13 ELEMENT MASS ISOMER DATA DATA-ERR MONIT 41070 2 14 NO-DIM NO-DIM NO-DIM PC/FIS PC/FIS PC/FIS 41070 2 15 42. 99. 4.16 0.40 4.35 41070 2 16 44. 103. 0. 6.25 0.80 4.35 41070 2 17 44. 106. 4.16 0.5 4.35 41070 2 18 47. 111. 0. 1.46 0.14 4.35 41070 2 19 48. 115. 0. 1.23 0.10 4.35 41070 2 20 48. 115. 1. 0.07 4.35 41070 2 21 52. 132. 4.58 0.50 4.35 41070 2 22 55. 137. 5.1 0.8 4.35 41070 2 23 ENDDATA 10 41070 2 24 ENDSUBENT 6 41070 299999 SUBENT 41070005 911105 41070 5 1 BIB 4 4 41070 5 2 REACTION (92-U-233(N,F)ELEM/MASS,CUM,FY) 41070 5 3 FACILITY (VDG) 41070 5 4 INC-SOURCE (D-T) 41070 5 5 MONITOR (92-U-233(N,F)58-CE-141,CUM,FY) 41070 5 6 ENDBIB 4 41070 5 7 COMMON 1 3 41070 5 8 EN 41070 5 9 EV 41070 5 10 14. E+06 41070 5 11 ENDCOMMON 1 3 41070 5 12 DATA 6 9 41070 5 13 ELEMENT MASS ISOMER DATA DATA-ERR MONIT 41070 5 14 NO-DIM NO-DIM NO-DIM PC/FIS PC/FIS PC/FIS 41070 5 15 42. 99. 3.5 0.3 5.0 41070 5 16 44. 103. 0. 2.31 0.30 5.0 41070 5 17 44. 106. 1.52 0.20 5.0 41070 5 18 47. 111. 0. 1.22 0.12 5.0 41070 5 19 48. 115. 0. 0.98 0.18 5.0 41070 5 20 48. 115. 1. 0.07 5.0 41070 5 21 52. 132. 3.98 0.35 5.0 41070 5 22 55. 136. 0. 0.5 5.0 41070 5 23 55. 137. 4.7 0.5 5.0 41070 5 24 ENDDATA 11 41070 5 25 ENDSUBENT 6 41070 599999 ENDENTRY 3 4107099999999 ENTRY 41072 950421 41072 0 1 SUBENT 41072001 950421 41072 1 1 BIB 9 15 41072 1 2 INSTITUTE (4RUSRI ) 41072 1 3 REFERENCE (J,RAK,4,(5),587,62) 41072 1 4 (J,SRA,4,515,62) ENGLISH TRANSLATION 41072 1 5 AUTHOR (A.N.APOLLONOVA,I.T.KRISYUK,V.N.USHATSKIY) 41072 1 6 TITLE DETERMINATION OF INDIVIDUAL YIELDS OF A = 139 ISOBARS 41072 1 7 IN URANIUM FISSION BY 14 MEV NEUTRONS 41072 1 8 METHOD (RCHEM) 41072 1 9 DETECTOR (FISCH) 41072 1 10 MONITOR NO INFORMATION 41072 1 11 ERR-ANALYS ERRORS NOT SPECIFIED 41072 1 12 HISTORY (911105T) CONVERTED FROM RIDER'S ENTRY 90214 41072 1 13 (930416A) INSTITUTE CODE 'KUR' CHANGED TO RI 41072 1 14 NEW DATA ADDED FROM REFERENCE ONE 41072 1 15 (940516A) .. REACTION CODE IN SAN 004 CORRECTED 41072 1 16 (950421U) .. KEYWORDS IN SAN 002 CORRECTED 41072 1 17 ENDBIB 15 41072 1 18 COMMON 1 3 41072 1 19 EN 41072 1 20 EV 41072 1 21 14. E+06 41072 1 22 ENDCOMMON 1 3 41072 1 23 ENDSUBENT 1 41072 199999 SUBENT 41072002 950421 41072 2 1 BIB 5 8 41072 2 2 REACTION ((92-U-238(N,F)ELEM/MASS,IND,FY)/ 41072 2 3 (92-U-238(N,F)MASS,CHN,FY)) 41072 2 4 RESULT (FRIND) 41072 2 5 ASSUMED (ASSUM1,92-U-238(N,F)55-CS-139,IND,FY) 41072 2 6 (ASSUM2,92-U-238(N,F)56-BA-139,IND,FY) 41072 2 7 STATUS (RIDER) RIDER'S REFERENCE 62APO1 41072 2 8 (DEP,41072003) 41072 2 9 HISTORY (950421U) ASSUM TO ASSUM1, ASSUM1 TO ASSUM2 CHANGED 41072 2 10 ENDBIB 8 41072 2 11 COMMON 2 3 41072 2 12 ASSUM1 ASSUM2 41072 2 13 NO-DIM NO-DIM 41072 2 14 0.286 0.056 41072 2 15 ENDCOMMON 2 3 41072 2 16 DATA 4 2 41072 2 17 ELEMENT MASS DATA DATA-ERR 41072 2 18 NO-DIM NO-DIM NO-DIM NO-DIM 41072 2 19 53. 139. 0.1830 0.020 41072 2 20 54. 139. 0.475 0.095 41072 2 21 ENDDATA 4 41072 2 22 ENDSUBENT 4 41072 299999 SUBENT 41072003 930416 41072 3 1 BIB 3 4 41072 3 2 REACTION ((92-U-238(N,F)54-XE-139,IND,FY)/ 41072 3 3 (92-U-238(N,F)53-I-139,IND,FY)) 41072 3 4 STATUS DATA ARE TAKEN FROM THE REFERENSE ONE 41072 3 5 HISTORY (930416C) COMPILED AT THE CENTRE - CJD 41072 3 6 ENDBIB 4 41072 3 7 NOCOMMON 0 0 41072 3 8 DATA 2 1 41072 3 9 DATA DATA-ERR 41072 3 10 NO-DIM NO-DIM 41072 3 11 2.6 0.3 41072 3 12 ENDDATA 3 41072 3 13 ENDSUBENT 2 41072 399999 ENDENTRY 3 4107299999999 ENTRY 41073 940517 41073 0 1 SUBENT 41073001 940517 41073 1 1 BIB 9 13 41073 1 2 INSTITUTE (4RUSRI ) 41073 1 3 REFERENCE (J,RAK,4,711,62) 41073 1 4 (J,SRA,4,631,62) ENGLISH TRANSLATION 41073 1 5 AUTHOR (A.N.APOLLONOVA,I.T.KRISYUK,V.N.USHATSKIY) 41073 1 6 TITLE PARTIAL YIELDS OF ISOBARS WITH A MASS NUMBER OF 138 41073 1 7 METHOD (RCHEM) 41073 1 8 MONITOR NO INFORMATION 41073 1 9 ERR-ANALYS ERRORS ARE NOT SPECIFIED 41073 1 10 STATUS (RIDER) RIDER'S REFERENCE 62APO2 41073 1 11 HISTORY (911105T) CONVERTED FROM RIDER'S ENTRY 90215 41073 1 12 (930419A) INSTITUTE CODE 'KUR' CHANGED TO RI 41073 1 13 NEW DATA ADDED FROM REFERENCE ONE 41073 1 14 (940517A) .. REACTION CODE IN SAN 004 CORRECTED 41073 1 15 ENDBIB 13 41073 1 16 COMMON 1 3 41073 1 17 EN 41073 1 18 EV 41073 1 19 14. E+06 41073 1 20 ENDCOMMON 1 3 41073 1 21 ENDSUBENT 1 41073 199999 SUBENT 41073002 930419 41073 2 1 BIB 3 4 41073 2 2 REACTION ((92-U-238(N,F)ELEM/MASS,CUM,FY)/ 41073 2 3 (92-U-238(N,F)MASS,CHN,FY)) 41073 2 4 RESULT (FRCUM) 41073 2 5 HISTORY (911105T) CONVERTED FROM RIDER'S SUBENTRY 90215002 41073 2 6 ENDBIB 4 41073 2 7 NOCOMMON 0 0 41073 2 8 DATA 4 1 41073 2 9 ELEMENT MASS DATA DATA-ERR 41073 2 10 NO-DIM NO-DIM NO-DIM NO-DIM 41073 2 11 53. 138. 5.50E-1 6.0E-2 41073 2 12 ENDDATA 3 41073 2 13 ENDSUBENT 4 41073 299999 SUBENT 41073003 930419 41073 3 1 BIB 4 5 41073 3 2 REACTION ((92-U-238(N,F)ELEM/MASS,IND,FY)/ 41073 3 3 (92-U-238(N,F)MASS,CHN,FY)) 41073 3 4 RESULT (FRIND) 41073 3 5 STATUS (DEP,41073004) 41073 3 6 HISTORY (911105T) CONVERTED FROM RIDER'S SUBENTRY 90215003 41073 3 7 ENDBIB 5 41073 3 8 NOCOMMON 0 0 41073 3 9 DATA 5 4 41073 3 10 ELEMENT MASS ISOMER DATA DATA-ERR 41073 3 11 NO-DIM NO-DIM NO-DIM NO-DIM NO-DIM 41073 3 12 52. 138. 0.120 0.006 41073 3 13 54. 138. 0.3670 0.040 41073 3 14 55. 138. 0. 8.30E-2 0.5E-2 41073 3 15 55. 138. 1. 8.30E-2 0.5E-2 41073 3 16 ENDDATA 6 41073 3 17 ENDSUBENT 5 41073 399999 SUBENT 41073005 930419 41073 5 1 BIB 3 4 41073 5 2 REACTION ((92-U-238(N,F)54-XE-138,CUM,FY)/ 41073 5 3 (92-U-238(N,F)53-I-138,CUM,FY)) 41073 5 4 ASSUMED (ASSUM,92-U-238(N,F)52-TE-138,IND,FY) 41073 5 5 HISTORY (930419C) COMPILED AT THE CENTRE - CJD 41073 5 6 ENDBIB 4 41073 5 7 NOCOMMON 0 0 41073 5 8 DATA 3 1 41073 5 9 DATA DATA-ERR ASSUM 41073 5 10 NO-DIM NO-DIM NO-DIM 41073 5 11 0.67 0.05 0.12 41073 5 12 ENDDATA 3 41073 5 13 ENDSUBENT 3 41073 599999 ENDENTRY 4 4107399999999 ENTRY 41074 911111 41074 0 1 SUBENT 41074001 911111 41074 1 1 BIB 10 13 41074 1 2 INSTITUTE (4CCPKUR) 41074 1 3 REFERENCE (J,YF,6,454,6709) IN RUSSIAN. 41074 1 4 (J,SNP,6,331,6803) ENGLISH TRANSLATION 41074 1 5 AUTHOR (N.I.BORISOVA,S.M.DUBROVINA,V.I.NOVGORODTSEVA, 41074 1 6 V.A.PCHELIN,V.A.SHIGIN,V.M.SHUBKO) 41074 1 7 TITLE VARIATION OF MASS DISTRIBUTIONS OF U-238 FISSION 41074 1 8 FRAGMENTS WITH NEUTRON ENERGY 41074 1 9 FACILITY (VDG) ELECTROSTATIC ACCELERATOR 41074 1 10 INC-SOURCE (P-T,D-D,D-T) 41074 1 11 METHOD (RCHEM) 41074 1 12 MONITOR NO INFORMATION 41074 1 13 ERR-ANALYS ERRORS ARE NOT GIVEN 41074 1 14 HISTORY (911111T) CONVERTED FROM RIDER'S ENTRY 90319, 90345 41074 1 15 ENDBIB 13 41074 1 16 NOCOMMON 0 0 41074 1 17 ENDSUBENT 0 41074 199999 SUBENT 41074002 911111 41074 2 1 BIB 2 3 41074 2 2 REACTION ((92-U-238(N,F)56-BA-140,CUM,FY)/ 41074 2 3 (92-U-238(N,F)ELEM/MASS,CUM,FY)) 41074 2 4 STATUS (RIDER) RIDER'S REFERENCE 67BOR1 41074 2 5 ENDBIB 3 41074 2 6 COMMON 1 3 41074 2 7 EN 41074 2 8 MEV 41074 2 9 18. 41074 2 10 ENDCOMMON 1 3 41074 2 11 DATA 4 2 41074 2 12 ELEMENT MASS ISOMER DATA 41074 2 13 NO-DIM NO-DIM NO-DIM NO-DIM 41074 2 14 33. 77. 160. 41074 2 15 48. 115. 0. 7. 41074 2 16 ENDDATA 4 41074 2 17 ENDSUBENT 4 41074 299999 SUBENT 41074003 911111 41074 3 1 BIB 2 3 41074 3 2 REACTION ((92-U-238(N,F)ELEM/MASS,CUM,FY)/ 41074 3 3 (92-U-238(N,F)42-MO-99,CUM,FY)) 41074 3 4 STATUS (RIDER) RIDER'S REFERENCE 67BOR1 41074 3 5 ENDBIB 3 41074 3 6 COMMON 1 3 41074 3 7 EN 41074 3 8 MEV 41074 3 9 18. 41074 3 10 ENDCOMMON 1 3 41074 3 11 DATA 4 3 41074 3 12 ELEMENT MASS ISOMER DATA 41074 3 13 NO-DIM NO-DIM NO-DIM NO-DIM 41074 3 14 33. 77. .00583 41074 3 15 47. 111. 0. .154 41074 3 16 48. 115. 0. .140 41074 3 17 ENDDATA 5 41074 3 18 ENDSUBENT 4 41074 399999 SUBENT 41074006 911111 41074 6 1 BIB 2 3 41074 6 2 REACTION ((92-U-238(N,F)ELEM/MASS,CUM,FY)/ 41074 6 3 (92-U-238(N,F)42-MO-99,CUM,FY)) 41074 6 4 STATUS (RIDER) RIDER'S REFERENCE 67BOR2 41074 6 5 ENDBIB 3 41074 6 6 NOCOMMON 0 0 41074 6 7 DATA 5 9 41074 6 8 EN ELEMENT MASS ISOMER DATA 41074 6 9 MEV NO-DIM NO-DIM NO-DIM NO-DIM 41074 6 10 13. 33. 77. .00456 41074 6 11 13. 47. 111. 0. .133 41074 6 12 13. 48. 115. 0. .106 41074 6 13 16. 33. 77. .00627 41074 6 14 16. 47. 111. 0. .172 41074 6 15 16. 48. 115. 0. .157 41074 6 16 18. 33. 77. .00555 41074 6 17 18. 47. 111. 0. .141 41074 6 18 18. 48. 115. 0. .131 41074 6 19 ENDDATA 11 41074 6 20 ENDSUBENT 5 41074 699999 ENDENTRY 4 4107499999999 ENTRY 41076 930412 41076 0 1 SUBENT 41076001 930412 41076 1 1 BIB 10 14 41076 1 2 INSTITUTE (4CCPRI ) 41076 1 3 REFERENCE (J,YF,6,919,68) 41076 1 4 (J,SNP,6,669,6805) 41076 1 5 AUTHOR (I.T.KRISYUK,A.N.PROTOPOPOV,N.T.USACHEVA) 41076 1 6 TITLE CONCERNING THE FINE STRUCTURE OF THE FRAGMENT MASS 41076 1 7 YIELD CURVE IN THE FISSION OF U235 BY 14-MEV NEUTRONS 41076 1 8 FACILITY (VDG) ELECTROSTATIC ACCELERATOR 41076 1 9 METHOD (RCHEM) 41076 1 10 MONITOR NO INFORMATION 41076 1 11 ERR-ANALYS ERRORS ARE NOT SPECIFIED 41076 1 12 STATUS (RIDER) RIDER'S REFERENCE 68KRI1 41076 1 13 HISTORY (911115T) CONVERTED FROM RIDER'S ENTRY 90354 41076 1 14 (920507U) SEVERAL KEYWORDS ADDED. ERRORS CORRECTED 41076 1 15 (930412U) INSTITUTE CODE 'KUR' CHANGED TO 'RI' 41076 1 16 ENDBIB 14 41076 1 17 NOCOMMON 0 0 41076 1 18 ENDSUBENT 0 41076 199999 SUBENT 41076002 920507 41076 2 1 BIB 2 4 41076 2 2 REACTION ((92-U-235(N,F)40-ZR-97,CUM,FY)/ 41076 2 3 (92-U-235(N,F)42-MO-99,CUM,FY)) 41076 2 4 HISTORY (920507U) ELEM/MASS IN SF4 CHANGED TO 40-ZR-97 41076 2 5 AND COLUMN NUMBER IN DATA SECTION REDUCED 41076 2 6 ENDBIB 4 41076 2 7 COMMON 1 3 41076 2 8 EN 41076 2 9 EV 41076 2 10 14. E+06 41076 2 11 ENDCOMMON 1 3 41076 2 12 DATA 2 1 41076 2 13 DATA DATA-ERR 41076 2 14 NO-DIM NO-DIM 41076 2 15 1.16 .02 41076 2 16 ENDDATA 3 41076 2 17 ENDSUBENT 2 41076 299999 ENDENTRY 2 4107699999999 ENTRY 41077 911116 41077 0 1 SUBENT 41077001 911116 41077 1 1 BIB 11 14 41077 1 2 INSTITUTE (4CCPTIL,4CCPRI ) 41077 1 3 REFERENCE (J,YF,11,1178,7006) 41077 1 4 (J,SNP,11,654,7012) ENGLISH TRANSLATION 41077 1 5 AUTHOR (K.A.PETRZHAK,V.F.TEPLYKH,M.G.PAN'YAN) 41077 1 6 TITLE MASS SPECTROMETRIC DETERMINATION OF XE ISOTOPE 41077 1 7 RELATIVE YIELDS FROM NATURAL URANIUM FISSION BY 14.7 41077 1 8 MEV NEUTRONS 41077 1 9 FACILITY (VDG) 41077 1 10 INC-SOURCE (D-T) 41077 1 11 METHOD (ASEP) 41077 1 12 MONITOR NO INFORMATION 41077 1 13 ERR-ANALYS ERRORS ARE NOT SPECIFIED 41077 1 14 STATUS (RIDER) RIDER'S REFERENCE 70PET1 41077 1 15 HISTORY (911116T) CONVERTED FROM RIDER'S ENTRY 90437 41077 1 16 ENDBIB 14 41077 1 17 COMMON 1 3 41077 1 18 EN 41077 1 19 MEV 41077 1 20 14.7 41077 1 21 ENDCOMMON 1 3 41077 1 22 ENDSUBENT 1 41077 199999 SUBENT 41077002 911116 41077 2 1 BIB 2 2 41077 2 2 REACTION (92-U-238(N,F)ELEM/MASS,CUM,FY) 41077 2 3 MONITOR (92-U-238(N,F)54-XE-134,CUM,FY) 41077 2 4 ENDBIB 2 41077 2 5 NOCOMMON 0 0 41077 2 6 DATA 6 3 41077 2 7 ELEMENT MASS ISOMER DATA DATA-ERR MONIT 41077 2 8 NO-DIM NO-DIM NO-DIM PC/FIS PC/FIS PC/FIS 41077 2 9 54. 131. 0. 18.64 .55 31.62 41077 2 10 54. 132. 23.06 .48 31.62 41077 2 11 54. 136. 26.62 .55 31.62 41077 2 12 ENDDATA 5 41077 2 13 ENDSUBENT 6 41077 299999 ENDENTRY 2 4107799999999 ENTRY 41082 911126 41082 0 1 SUBENT 41082001 911126 41082 1 1 BIB 10 12 41082 1 2 INSTITUTE (4CCPKUR) 41082 1 3 REFERENCE (J,YF,17,(3),470,7303) 41082 1 4 AUTHOR (S.M.DUBROVINA,V.I.NOVGORODTSEVA,L.N.MOROZOV, 41082 1 5 V.A.PCHELIN,L.V.CHISTYAKOV,V.A.SHIGIN,V.M.SHUBKO) 41082 1 6 TITLE CHANGES OF MASS DISTRIBUTION OF FRAGMENTS FROM TH232 41082 1 7 FISSION WITH NEUTRON ENERGY 41082 1 8 FACILITY (VDG) 41082 1 9 METHOD (RCHEM) 41082 1 10 MONITOR NO INFORMATION 41082 1 11 ERR-ANALYS NO INFORMATION 41082 1 12 STATUS (RIDER) RIDER' REFERENCE 73DUB1 41082 1 13 HISTORY (911126T) RIDER'S ENTRY 90552 41082 1 14 ENDBIB 12 41082 1 15 NOCOMMON 0 0 41082 1 16 ENDSUBENT 0 41082 199999 SUBENT 41082003 911126 41082 3 1 BIB 1 2 41082 3 2 REACTION ((90-TH-232(N,F)ELEM/MASS,CUM,FY)/ 41082 3 3 (90-TH-232(N,F)38-SR-89,CUM,FY)) 41082 3 4 ENDBIB 2 41082 3 5 COMMON 1 3 41082 3 6 EN 41082 3 7 MEV 41082 3 8 14. 41082 3 9 ENDCOMMON 1 3 41082 3 10 DATA 4 6 41082 3 11 ELEMENT MASS ISOMER DATA 41082 3 12 NO-DIM NO-DIM NO-DIM NO-DIM 41082 3 13 33. 77. 7.0E-3 41082 3 14 42. 99. 0.36 41082 3 15 48. 115. 0. 1.6E-1 41082 3 16 50. 121. 0. 1.0E-1 41082 3 17 50. 125. 0. 4.7E-2 41082 3 18 56. 140. 0.9 41082 3 19 ENDDATA 8 41082 3 20 ENDSUBENT 4 41082 399999 ENDENTRY 2 4108299999999 ENTRY 41087 931014 41087 0 1 SUBENT 41087001 931014 41087 1 1 BIB 10 17 41087 1 2 INSTITUTE (4CCPRI ,4CCPTIL) 41087 1 3 REFERENCE (J,AE,42,337,7704) 41087 1 4 (J,SJA,42,379,7710) 41087 1 5 AUTHOR (K.A.PETRZHAK,E.V.PLATYGINA,V.F.TEPLYKH) 41087 1 6 TITLE THE FINE STRUCTURE OF HEAVY NUCLEI FISSION FRAGMENT 41087 1 7 YIELDS 41087 1 8 FACILITY (LINAC,4CCPRI) 41087 1 9 METHOD (ASEP) 41087 1 10 MONITOR NO INFORMATION 41087 1 11 ERR-ANALYS ERRORS ARE NOT SPECIFIED 41087 1 12 STATUS (RIDER) RIDER'S REFERENCE 77PET1 41087 1 13 HISTORY (911209T) CONVERTED FROM RIDER'S ENTRY 90706 41087 1 14 (920814U) UNITS CHANGED FROM PC/FIS TO ARB-UNITS 41087 1 15 MONITOR VALUES MOVED TO COMMON SECTION 41087 1 16 ONE MORE INSTITUTE CODE ADDED 41087 1 17 (931014U) MONITOR IN SAN 001-004 DELETED 41087 1 18 INCIDENT NEUTRON ENERGY CORRECTED 41087 1 19 ENDBIB 17 41087 1 20 COMMON 1 3 41087 1 21 EN 41087 1 22 EV 41087 1 23 14.7 E+06 41087 1 24 ENDCOMMON 1 3 41087 1 25 ENDSUBENT 1 41087 199999 SUBENT 41087002 931014 41087 2 1 BIB 2 3 41087 2 2 REACTION (94-PU-239(N,F)ELEM/MASS,CUM,FY,,REL) 41087 2 3 HISTORY (931014U) MONITOR KEYWORD DELETED 41087 2 4 MONIT VALUE ADDED TO DATA TABLE 41087 2 5 ENDBIB 3 41087 2 6 NOCOMMON 0 0 41087 2 7 DATA 4 4 41087 2 8 ELEMENT MASS DATA DATA-ERR 41087 2 9 NO-DIM NO-DIM ARB-UNITS ARB-UNITS 41087 2 10 54. 131. 20.5 0.3 41087 2 11 54. 132. 24.9 0.3 41087 2 12 54. 134. 28.5 0.3 41087 2 13 54. 136. 25.75 0.3 41087 2 14 ENDDATA 6 41087 2 15 ENDSUBENT 4 41087 299999 SUBENT 41087003 931014 41087 3 1 BIB 2 3 41087 3 2 REACTION (90-TH-232(N,F)ELEM/MASS,CUM,FY,,REL) 41087 3 3 HISTORY (931014U) MONITOR KEYWORD DELETED 41087 3 4 MONIT VALUE ADDED TO DATA TABLE 41087 3 5 ENDBIB 3 41087 3 6 NOCOMMON 0 0 41087 3 7 DATA 4 4 41087 3 8 ELEMENT MASS DATA DATA-ERR 41087 3 9 NO-DIM NO-DIM ARB-UNITS ARB-UNITS 41087 3 10 54. 131. 14.15 0.3 41087 3 11 54. 132. 18.8 0.3 41087 3 12 54. 134. 28.7 0.75 41087 3 13 54. 136. 38.25 0.4 41087 3 14 ENDDATA 6 41087 3 15 ENDSUBENT 4 41087 399999 SUBENT 41087004 931014 41087 4 1 BIB 2 3 41087 4 2 REACTION (92-U-235(N,F)ELEM/MASS,CUM,FY,,REL) 41087 4 3 HISTORY (931014U) MONITOR KEYWORD DELETED. 41087 4 4 MONIT VALUE ADDED TO DATA TABLE 41087 4 5 ENDBIB 3 41087 4 6 NOCOMMON 0 0 41087 4 7 DATA 4 4 41087 4 8 ELEMENT MASS DATA DATA-ERR 41087 4 9 NO-DIM NO-DIM ARB-UNITS ARB-UNITS 41087 4 10 54. 131. 20.75 0.3 41087 4 11 54. 132. 25.05 0.4 41087 4 12 54. 134. 28.35 0.4 41087 4 13 54. 136. 25.85 0.4 41087 4 14 ENDDATA 6 41087 4 15 ENDSUBENT 4 41087 499999 ENDENTRY 4 4108799999999 ENTRY 41117 930921 41117 0 1 SUBENT 41117001 930921 41117 1 1 BIB 9 13 41117 1 2 INSTITUTE (4RUSRI ) 41117 1 3 REFERENCE (J,YK,,(1),18,92) DATA TABLE IS GIVEN 41117 1 4 AUTHOR (L.V.DRAPCHINSKIY,O.I.KOSTOCHKIN,V.A.TRENKIN) 41117 1 5 TITLE TRITIUM YIELD MEASUREMENT AT THE NUCLEI NEUTRON 41117 1 6 FISSION 41117 1 7 DETECTOR (CSICR) 41117 1 8 MONITOR NO INFORMATION 41117 1 9 ERR-ANALYS (DATA-ERR) ERROR IS NOT SPECIFIED 41117 1 10 STATUS DATA ARE TAKEN FROM THE REFERENCE 41117 1 11 HISTORY (930616C) + + COMPILED AT THE CENTRE - CJD + + 41117 1 12 (930921A) / / REACTION SF4 FIELDS CORRECTED IN 41117 1 13 ALL SUBENTS AND NUMERICAL VALUES CORRECTED IN 41117 1 14 SEVERAL SUBENTS . . 41117 1 15 ENDBIB 13 41117 1 16 NOCOMMON 0 0 41117 1 17 ENDSUBENT 0 41117 199999 SUBENT 41117002 930921 41117 2 1 BIB 1 2 41117 2 2 REACTION ((92-U-235(N,F)1-H-3,PRE,FY)/ 41117 2 3 (92-U-235(N,F)2-HE-4,PRE,FY)) 41117 2 4 ENDBIB 2 41117 2 5 NOCOMMON 0 0 41117 2 6 DATA 3 1 41117 2 7 EN DATA DATA-ERR 41117 2 8 MEV NO-DIM NO-DIM 41117 2 9 14.5 7.0 E-02 6.E-03 41117 2 10 ENDDATA 3 41117 2 11 ENDSUBENT 3 41117 299999 SUBENT 41117003 930921 41117 3 1 BIB 3 5 41117 3 2 REACTION 1(92-U-235(N,F)1-H-3,PRE,FY) 41117 3 3 2(92-U-235(N,F)1-H-3,PRE,FY) 41117 3 4 ANALYSIS 1 DATA OBTAINED USING Z**2/A SYSTEMATICS 41117 3 5 2 DATA OBTAINED USING 4*Z-A SYSTEMATICS 41117 3 6 HISTORY (930921A) NUMERICAL VALUES CORRECTED 41117 3 7 ENDBIB 5 41117 3 8 NOCOMMON 0 0 41117 3 9 DATA 5 1 41117 3 10 EN DATA 1DATA-ERR 1DATA 2DATA-ERR 2 41117 3 11 MEV PC/FIS PC/FIS PC/FIS PC/FIS 41117 3 12 14.5 1.28E-02 1.1E-03 1.18E-02 1.0E-03 41117 3 13 ENDDATA 3 41117 3 14 ENDSUBENT 5 41117 399999 SUBENT 41117004 930921 41117 4 1 BIB 2 3 41117 4 2 REACTION ((92-U-233(N,F)1-H-3,PRE,FY)/ 41117 4 3 (92-U-233(N,F)2-HE-4,PRE,FY)) 41117 4 4 HISTORY (930921A) SF4 IN REACTION FIELD CORRECTED 41117 4 5 ENDBIB 3 41117 4 6 NOCOMMON 0 0 41117 4 7 DATA 3 1 41117 4 8 EN DATA DATA-ERR 41117 4 9 MEV NO-DIM NO-DIM 41117 4 10 14.5 6.1 E-02 5. E-03 41117 4 11 ENDDATA 3 41117 4 12 ENDSUBENT 3 41117 499999 SUBENT 41117005 930921 41117 5 1 BIB 3 5 41117 5 2 REACTION 1(92-U-233(N,F)1-H-3,PRE,FY) 41117 5 3 2(92-U-233(N,F)1-H-3,PRE,FY) 41117 5 4 ANALYSIS 1 DATA OBTAINED USING Z**2/A SYSTEMATICS 41117 5 5 2 DATA OBTAINED USING 4*Z-A SYSTEMATICS 41117 5 6 HISTORY (930921A) NUMERICAL VALUES CORRECTED 41117 5 7 ENDBIB 5 41117 5 8 NOCOMMON 0 0 41117 5 9 DATA 5 1 41117 5 10 EN DATA 1DATA-ERR 1DATA 2DATA-ERR 2 41117 5 11 MEV PC/FIS PC/FIS PC/FIS PC/FIS 41117 5 12 14.5 1.33E-02 1.1E-03 1.25E-02 1.0E-03 41117 5 13 ENDDATA 3 41117 5 14 ENDSUBENT 5 41117 599999 SUBENT 41117006 930921 41117 6 1 BIB 2 3 41117 6 2 REACTION ((94-PU-240(N,F)1-H-3,PRE,FY)/ 41117 6 3 (94-PU-240(N,F)2-HE-4,PRE,FY)) 41117 6 4 HISTORY (930921A) NUMERICAL VALUES CORRECTED 41117 6 5 ENDBIB 3 41117 6 6 NOCOMMON 0 0 41117 6 7 DATA 3 1 41117 6 8 EN DATA DATA-ERR 41117 6 9 MEV NO-DIM NO-DIM 41117 6 10 14.5 9.0 E-02 9. E-03 41117 6 11 ENDDATA 3 41117 6 12 ENDSUBENT 3 41117 699999 SUBENT 41117007 930921 41117 7 1 BIB 3 5 41117 7 2 REACTION 1(94-PU-240(N,F)1-H-3,PRE,FY) 41117 7 3 2(94-PU-240(N,F)1-H-3,PRE,FY) 41117 7 4 ANALYSIS 1 DATA OBTAINED USING Z**2/A SYSTEMATICS 41117 7 5 2 DATA OBTAINED USING 4*Z-A SYSTEMATICS 41117 7 6 HISTORY (930921A) NUMERICAL VALUEY CORRECTED 41117 7 7 ENDBIB 5 41117 7 8 NOCOMMON 0 0 41117 7 9 DATA 5 1 41117 7 10 EN DATA 1DATA-ERR 1DATA 2DATA-ERR 2 41117 7 11 MEV PC/FIS PC/FIS PC/FIS PC/FIS 41117 7 12 14.5 1.37E-02 1.4E-03 1.95E-02 2.0E-03 41117 7 13 ENDDATA 3 41117 7 14 ENDSUBENT 5 41117 799999 ENDENTRY 7 4111799999999 ENTRY 41157 940914 41157 0 1 SUBENT 41157001 940914 41157 1 1 BIB 11 23 41157 1 2 INSTITUTE (4RUSMIF,4RUSFEI,4RUSLIN) 41157 1 3 REFERENCE (J,RCA,57,69,92) DATA TABLES ARE GIVEN 41157 1 4 (R,MIF-058-88,88) PRELIMINARY PUBLICATION 41157 1 5 AUTHOR (A.N.GUDKOV,S.V.KRIVASHEEV,A.B.KOLDOBSKIY, 41157 1 6 V.V.KOVALENKO,E.YU.BOBKOV,V.M.ZHIVUN) 41157 1 7 TITLE YIELDS OF DELAYED NEUTRON PRECURSORS IN THE FISSION 41157 1 8 OF ACTINIDES 41157 1 9 DETECTOR (BF3) BATTERY OF 24 BF3 COUNTERS 41157 1 10 ANALYSIS METHOD OF INCREMENTAL DECONVOLUTION, T.J.KENNETT, 41157 1 11 W.V.PRESTWICH, NUCL.INSTR. AND METHODS, VOL.203, P.31 41157 1 12 1982 41157 1 13 MONITOR NO INFORMATION 41157 1 14 DECAY-DATA (35-BR-87,55.7SEC) 41157 1 15 (35-BR-88,16.0SEC) 41157 1 16 (35-BR-89,4.38SEC) 41157 1 17 (37-RB-93,5.86SEC) 41157 1 18 (37-RB-94,2.76SEC) 41157 1 19 (53-I-137,24.5SEC) 41157 1 20 (53-I-138,6.53SEC) 41157 1 21 (53-I-139,2.38SEC) 41157 1 22 ERR-ANALYS (ERR-T) TOTAL ERROR 41157 1 23 STATUS DATA ARE TAKEN FROM THE REFERENCE ONE 41157 1 24 HISTORY (940914C) + + COMPILED AT THE CENTRE - CJD + + 41157 1 25 ENDBIB 23 41157 1 26 NOCOMMON 0 0 41157 1 27 ENDSUBENT 0 41157 199999 SUBENT 41157013 940914 41157 13 1 BIB 2 2 41157 13 2 REACTION (92-U-235(N,F)ELEM/MASS,CUM,FY) 41157 13 3 FACILITY (VDG,4RUSLIN) 41157 13 4 ENDBIB 2 41157 13 5 COMMON 1 3 41157 13 6 EN 41157 13 7 EV 41157 13 8 1.47E+07 41157 13 9 ENDCOMMON 1 3 41157 13 10 DATA 4 8 41157 13 11 ELEMENT MASS DATA ERR-T 41157 13 12 NO-DIM NO-DIM PC/FIS PC/FIS 41157 13 13 35. 87. 1.82 0.22 41157 13 14 35. 88. 1.41 0.28 41157 13 15 35. 89. 0.88 0.37 41157 13 16 37. 93. 2.21 0.48 41157 13 17 37. 94. 1.32 0.59 41157 13 18 53. 137. 1.37 0.21 41157 13 19 53. 138. 1.18 0.33 41157 13 20 53. 139. 0.22 0.12 41157 13 21 ENDDATA 10 41157 13 22 ENDSUBENT 4 41157 1399999 SUBENT 41157014 940914 41157 14 1 BIB 2 2 41157 14 2 REACTION (92-U-236(N,F)ELEM/MASS,CUM,FY) 41157 14 3 FACILITY (VDG,4RUSLIN) 41157 14 4 ENDBIB 2 41157 14 5 COMMON 1 3 41157 14 6 EN 41157 14 7 EV 41157 14 8 1.47E+07 41157 14 9 ENDCOMMON 1 3 41157 14 10 DATA 4 8 41157 14 11 ELEMENT MASS DATA ERR-T 41157 14 12 NO-DIM NO-DIM PC/FIS PC/FIS 41157 14 13 35. 87. 1.29 0.29 41157 14 14 35. 88. 1.57 0.40 41157 14 15 35. 89. 0.70 0.23 41157 14 16 37. 93. 1.58 0.87 41157 14 17 37. 94. 1.50 0.59 41157 14 18 53. 137. 1.85 0.45 41157 14 19 53. 138. 1.10 0.35 41157 14 20 53. 139. 0.47 0.17 41157 14 21 ENDDATA 10 41157 14 22 ENDSUBENT 4 41157 1499999 SUBENT 41157015 940914 41157 15 1 BIB 2 2 41157 15 2 REACTION (92-U-238(N,F)ELEM/MASS,CUM,FY) 41157 15 3 FACILITY (VDG,4RUSLIN) 41157 15 4 ENDBIB 2 41157 15 5 COMMON 1 3 41157 15 6 EN 41157 15 7 EV 41157 15 8 1.47E+07 41157 15 9 ENDCOMMON 1 3 41157 15 10 DATA 4 8 41157 15 11 ELEMENT MASS DATA ERR-T 41157 15 12 NO-DIM NO-DIM PC/FIS PC/FIS 41157 15 13 35. 87. 1.94 0.31 41157 15 14 35. 88. 1.90 0.37 41157 15 15 35. 89. 1.19 0.20 41157 15 16 37. 93. 4.77 1.22 41157 15 17 37. 94. 2.67 0.78 41157 15 18 53. 137. 3.28 0.66 41157 15 19 53. 138. 1.94 0.33 41157 15 20 53. 139. 0.37 0.19 41157 15 21 ENDDATA 10 41157 15 22 ENDSUBENT 4 41157 1599999 SUBENT 41157016 940914 41157 16 1 BIB 2 2 41157 16 2 REACTION (93-NP-237(N,F)ELEM/MASS,CUM,FY) 41157 16 3 FACILITY (VDG,4RUSLIN) 41157 16 4 ENDBIB 2 41157 16 5 COMMON 1 3 41157 16 6 EN 41157 16 7 EV 41157 16 8 1.47E+07 41157 16 9 ENDCOMMON 1 3 41157 16 10 DATA 4 8 41157 16 11 ELEMENT MASS DATA ERR-T 41157 16 12 NO-DIM NO-DIM PC/FIS PC/FIS 41157 16 13 35. 87. 1.11 0.18 41157 16 14 35. 88. 0.80 0.15 41157 16 15 35. 89. 0.34 0.07 41157 16 16 37. 93. 3.55 1.03 41157 16 17 37. 94. 0.42 0.17 41157 16 18 53. 137. 0.77 0.14 41157 16 19 53. 138. 0.44 0.10 41157 16 20 53. 139. 0.16 0.06 41157 16 21 ENDDATA 10 41157 16 22 ENDSUBENT 4 41157 1699999 SUBENT 41157017 940914 41157 17 1 BIB 2 2 41157 17 2 REACTION (94-PU-242(N,F)ELEM/MASS,CUM,FY) 41157 17 3 FACILITY (VDG,4RUSLIN) 41157 17 4 ENDBIB 2 41157 17 5 COMMON 1 3 41157 17 6 EN 41157 17 7 EV 41157 17 8 1.47E+07 41157 17 9 ENDCOMMON 1 3 41157 17 10 DATA 4 8 41157 17 11 ELEMENT MASS DATA ERR-T 41157 17 12 NO-DIM NO-DIM PC/FIS PC/FIS 41157 17 13 35. 87. 1.04 0.20 41157 17 14 35. 88. 1.00 0.23 41157 17 15 35. 89. 0.39 0.12 41157 17 16 37. 93. 3.52 0.94 41157 17 17 37. 94. 0.74 0.27 41157 17 18 53. 137. 1.65 0.34 41157 17 19 53. 138. 0.82 0.27 41157 17 20 53. 139. 0.25 0.12 41157 17 21 ENDDATA 10 41157 17 22 ENDSUBENT 4 41157 1799999 ENDENTRY 6 4115799999999 ENDREQUEST 101 Z999999999999