ENTRY 23362 20171020 226823362 0 1 SUBENT 23362001 20171020 226823362 1 1 BIB 13 33 23362 1 2 REFERENCE (C,69VIENNA,,591,1969) 23362 1 3 AUTHOR (H.D.Schuessler,H.Ahrens,H.Folger,H.Franz,W.Grimm, 23362 1 4 G.Herrmann,J.V.Kratz,K.L.Kratz) 23362 1 5 TITLE Delayed neutron precursors in fission of U-235 by 23362 1 6 thermal neutrons 23362 1 7 INSTITUTE (2GERMNZ) 23362 1 8 FACILITY (REAC,2GERMNZ) 23362 1 9 INC-SOURCE (REAC) 23362 1 10 INC-SPECT Thermal flux. 23362 1 11 SAMPLE - 2cm3 of U solution in polystyrene capsule - at 23362 1 12 ion or isotope exchange method. 23362 1 13 - Thin film UO(2) deposited on Ai foil - at recoil 23362 1 14 reaction method. 23362 1 15 - About 1 cm3 of U solution in thin glass capsule - 23362 1 16 at method of separation by volatization. 23362 1 17 METHOD (CHSEP) Chemical separation by rapid automatic 23362 1 18 technique. Chemical steps: 23362 1 19 - isotopic or ion exchange with preformed precipitates 23362 1 20 (Br,I,Rb,Cs,Sr), min.time 3.0sec, 23362 1 21 - extraction into quasi-solid reagents (Y,Zr,Nb), 23362 1 22 - volatization as hydrides (As,Se,Sb,Te), separation 23362 1 23 time 4-5 sec, 23362 1 24 - recoil reactions with methane forming volatile methyl23362 1 25 halides (Br,I), separation within 0.5 sec. 23362 1 26 PART-DET (N,DG) Neutron decay curves, gamma spectra. 23362 1 27 DETECTOR (GELI) Ge(Li)-detectors. For gamma-spectra . 23362 1 28 (HE3SP) Six He-3 counting tubes as neutron detector , 23362 1 29 an counters for beta rays . 23362 1 30 ANALYSIS The absolute yields of Br-88 and I-137 are the basis 23362 1 31 for calculating the absolute yields of other precursors23362 1 32 whose intensities were measured relative to these 23362 1 33 standard nuclides. 23362 1 34 HISTORY (20171020C) M.M. 23362 1 35 ENDBIB 33 0 23362 1 36 NOCOMMON 0 0 23362 1 37 ENDSUBENT 36 0 23362 199999 SUBENT 23362002 20171020 226823362 2 1 BIB 6 11 23362 2 2 REACTION (92-U-235(N,F),DL/GRP,NU,,MXW) 23362 2 3 Delayed neutron yield for specific group of half-life 23362 2 4 ANALYSIS Unseparated sample was measured and analyzed. 23362 2 5 FLAG (1.) these data for 0.6 and 0.2 sec groups, preliminary23362 2 6 results. 23362 2 7 MISC-COL (MISC) Contribution of non-halogens to the longest 23362 2 8 groups 23362 2 9 ERR-ANALYS (DATA-ERR) Type of error is not explained in the 23362 2 10 article 23362 2 11 (MISC-ERR) Absolute error of MISC 23362 2 12 STATUS (TABLE) Table III Cconf.Proc. 69VIENNA,,591,1969 23362 2 13 ENDBIB 11 0 23362 2 14 COMMON 1 3 23362 2 15 EN-DUMMY 23362 2 16 EV 23362 2 17 0.0253 23362 2 18 ENDCOMMON 3 0 23362 2 19 DATA 7 5 23362 2 20 GRP-NUM HL DATA DATA-ERR FLAG MISC 23362 2 21 MISC-ERR 23362 2 22 NO-DIM SEC PC/FIS PC/FIS NO-DIM PER-CENT 23362 2 23 PER-CENT 23362 2 24 1. 55. 5.9E-2 0.9E-2 0.4 23362 2 25 1.0 23362 2 26 2. 22. 34.6E-2 1.8E-2 2.3 23362 2 27 1.5 23362 2 28 3. 6. 31.5E-2 5.4E-2 23. 23362 2 29 5. 23362 2 30 4. 2. 60.2E-2 7.8E-2 44. 23362 2 31 10. 23362 2 32 5. 0.6 26.0E-2 10.6E-2 1. 23362 2 33 23362 2 34 ENDDATA 14 0 23362 2 35 ENDSUBENT 34 0 23362 299999 SUBENT 23362003 20171020 226823362 3 1 BIB 6 26 23362 3 2 REACTION (92-U-235(N,F)ELEM/MASS,DL/CUM,NU) 23362 3 3 Delayed neutron yield for specific isotope 23362 3 4 DECAY-DATA ((3.)35-BR-87,54.5SEC) 23362 3 5 ((4.)35-BR-88,16.3SEC) 23362 3 6 ((5.)35-BR-89,4.4SEC) 23362 3 7 ((6.)35-BR-90,1.6SEC) 23362 3 8 ((7.)35-BR-91,0.5SEC) 23362 3 9 ((8.)37-RB-93,6.2SEC) 23362 3 10 ((9.)37-RB-94,2.3SEC) 23362 3 11 ((10.)39-Y-98,2.3SEC) 23362 3 12 ((11.)52-TE-136,20.SEC) 23362 3 13 ((12.)52-TE-137,3.5SEC) 23362 3 14 ((13.)53-I-137,24.4SEC) 23362 3 15 ((14.)53-I-138,6.3SEC) 23362 3 16 ((15.)53-I-139,2.0SEC) 23362 3 17 ((16.)53-I-140,0.8SEC) 23362 3 18 ((17.)53-I-141,0.4SEC) 23362 3 19 COMMENT Of authors. For Te-137 data are average of values 23362 3 20 from this work, Tomlison and del Marmol . 23362 3 21 Of compiler. Data for Se-87,88 are in Subent 023 . 23362 3 22 REL-REF (R,23349001,L.Tomlison+,J,JIN,30,1649,1968) 23362 3 23 (R,23350001,L.Tomlison+,J,JIN,30,1995,1968) 23362 3 24 (R,,P.del Marmol+,J,JIN,29,273,1967) 23362 3 25 ERR-ANALYS (DATA-ERR) Type of error is not explained in the 23362 3 26 article 23362 3 27 STATUS (TABLE) Tables III, IV of Conf.Proc. 69VIENNA,,591,196923362 3 28 ENDBIB 26 0 23362 3 29 COMMON 1 3 23362 3 30 EN-DUMMY 23362 3 31 EV 23362 3 32 0.0253 23362 3 33 ENDCOMMON 3 0 23362 3 34 DATA 6 15 23362 3 35 ELEMENT MASS DATA DATA-ERR DATA-APRX DECAY-FLAG 23362 3 36 NO-DIM NO-DIM PC/FIS PC/FIS PC/FIS NO-DIM 23362 3 37 35. 87. 5.6E-2 0.3E-2 3. 23362 3 38 35. 88. 12.1E-2 1.5E-2 4. 23362 3 39 35. 89. 17.7E-2 4.2E-2 5. 23362 3 40 35. 90. 14.3E-2 3.5E-2 6. 23362 3 41 35. 91. 1.8E-2 0.7E-2 7. 23362 3 42 37. 93. 6.6E-2 1.7E-2 8. 23362 3 43 37. 94. 16.9E-2 3.5E-2 9. 23362 3 44 39. 98. 1.8E-2 0.9E-2 10. 23362 3 45 52. 136. 1.2E-2 11. 23362 3 46 52. 137. 0.7E-2 12. 23362 3 47 53. 137. 21.7E-2 2.6E-2 13. 23362 3 48 53. 138. 8.0E-2 1.9E-2 14. 23362 3 49 53. 139. 9.9E-2 2.2E-2 15. 23362 3 50 53. 140. 6.4E-2 3.5E-2 16. 23362 3 51 53. 141. 2.1E-2 0.7E-2 17. 23362 3 52 ENDDATA 17 0 23362 3 53 ENDSUBENT 52 0 23362 399999 SUBENT 23362004 20171020 226823362 4 1 BIB 6 15 23362 4 2 REACTION ((92-U-235(N,F)33-AS-85,DL/CUM,NU)+ 23362 4 3 (92-U-235(N,F)33-AS-86,DL/CUM,NU)) 23362 4 4 Delayed neutron yield for specific As isotopes 23362 4 5 ANALYSIS As-85 HL was defined from neutron decay curves to be 23362 4 6 ~2.1sec 23362 4 7 DECAY-DATA (33-AS-85,2.03SEC) 23362 4 8 ADD-RES (DECAY) Half-lives were determined for 23362 4 9 As-83 - 13.1+-0.4 sec from gamma-ray spectra' 23362 4 10 As-84 - ~5.6sec from gamma-ray spectra, 6.+-1 sec from 23362 4 11 gamma-ray spectra for counted Se-84, 23362 4 12 As-87 - ~1.sec from neutron decay curve for counted 23362 4 13 Br-87 . 23362 4 14 ERR-ANALYS (DATA-ERR) Type of error is not explained in the 23362 4 15 article 23362 4 16 STATUS (TABLE) Table III of Conf.Proc. 69VIENNA,,591,1969 23362 4 17 ENDBIB 15 0 23362 4 18 COMMON 1 3 23362 4 19 EN-DUMMY 23362 4 20 EV 23362 4 21 0.0253 23362 4 22 ENDCOMMON 3 0 23362 4 23 DATA 2 1 23362 4 24 DATA DATA-ERR 23362 4 25 PC/FIS PC/FIS 23362 4 26 7.7E-2 0.8E-2 23362 4 27 ENDDATA 3 0 23362 4 28 ENDSUBENT 27 0 23362 499999 SUBENT 23362005 20171020 226823362 5 1 BIB 8 18 23362 5 2 REACTION (34-SE-87(0,B-)35-BR-87,,PN) 23362 5 3 REL-REF (A,23350003,L.Tomlinson+,J,JIN,30,1995,1968) 23362 5 4 < or = 0.8 % 23362 5 5 ANALYSIS - Se-87 HL was defined from neutron decay curve to be 23362 5 6 5.9+-0.2 sec (for counted Se-87 and Br-87 - the same 23362 5 7 value obtained). 23362 5 8 - Neutron emission probabilities were derived by 23362 5 9 dividing the neutron yields by the cumulative fission 23362 5 10 yields of the precursor. 23362 5 11 ASSUMED (ASSUM,92-U-235(N,F)34-SE-87,CUM,FY) 23362 5 12 DECAY-DATA (34-SE-87,5.9SEC) 23362 5 13 ADD-RES (DECAY) Se-86 half-live was determined from gamma-ray 23362 5 14 spectra to be 16.7+-0.3 sec . 23362 5 15 ERR-ANALYS (DATA-ERR) Type of error is not explained in the 23362 5 16 article 23362 5 17 STATUS (TABLE) Table IV of Conf.Proc. 69VIENNA,,591,1969 23362 5 18 (DEP,23362003) Delayed neutron yield . 23362 5 19 (SPSDD,22047006) Superseded by newer publication(1970) 23362 5 20 ENDBIB 18 0 23362 5 21 COMMON 2 3 23362 5 22 EN-NRM ASSUM 23362 5 23 EV PC/FIS 23362 5 24 0.0253 1.2 23362 5 25 ENDCOMMON 3 0 23362 5 26 DATA 2 1 23362 5 27 DATA DATA-ERR 23362 5 28 NO-DIM NO-DIM 23362 5 29 0.3E-2 0.1E-2 23362 5 30 ENDDATA 3 0 23362 5 31 ENDSUBENT 30 0 23362 599999 SUBENT 23362006 20171020 226823362 6 1 BIB 6 14 23362 6 2 REACTION (34-SE-88(0,B-)35-BR-88,,PN) 23362 6 3 ANALYSIS - Se-88 HL was defined from neutron decay curves to be 23362 6 4 ~2sec, from neutron decay curve for counted Br-88 - 23362 6 5 1.7+-0.5 sec. 23362 6 6 - Neutron emission probabilities were derived by 23362 6 7 dividing the neutron yields by the cumulative fission 23362 6 8 yields of the precursor. 23362 6 9 ASSUMED (ASSUM,92-U-235(N,F)34-SE-88,CUM,FY) 23362 6 10 DECAY-DATA (34-SE-88,2.SEC) 23362 6 11 ERR-ANALYS (DATA-ERR) Type of error is not explained in the 23362 6 12 article 23362 6 13 STATUS (TABLE) Table IV of Conf.Proc. 69VIENNA,,591,1969 23362 6 14 (DEP,23362003) Delayed neutron yield . 23362 6 15 (SPSDD,22047007) Superseded by newer publication(1970) 23362 6 16 ENDBIB 14 0 23362 6 17 COMMON 2 3 23362 6 18 EN-NRM ASSUM 23362 6 19 EV PC/FIS 23362 6 20 0.0253 0.8 23362 6 21 ENDCOMMON 3 0 23362 6 22 DATA 2 1 23362 6 23 DATA DATA-ERR 23362 6 24 NO-DIM NO-DIM 23362 6 25 0.4E-2 0.2E-2 23362 6 26 ENDDATA 3 0 23362 6 27 ENDSUBENT 26 0 23362 699999 SUBENT 23362007 20171020 226823362 7 1 BIB 7 16 23362 7 2 REACTION (35-BR-87(0,B-)36-KR-87,,PN) 23362 7 3 REL-REF (A,41617002,P.M.Aron+,J,SJA,16,447,1964) 23362 7 4 Engl.translation of: 23362 7 5 (A,41617002,P.M.Aron+,J,AE,16,368,1964) 23362 7 6 3.1+-0.6 % 23362 7 7 ANALYSIS - Neutron emission probabilities were derived by 23362 7 8 dividing the neutron yields by the cumulative fission 23362 7 9 yields of the precursor. 23362 7 10 ASSUMED (ASSUM,92-U-235(N,F)35-BR-87,CUM,FY) 23362 7 11 DECAY-DATA (35-BR-87,54.5SEC) 23362 7 12 ERR-ANALYS (DATA-ERR) Type of error is not explained in the 23362 7 13 article 23362 7 14 STATUS (TABLE) Table IV of Conf.Proc. 69VIENNA,,591,1969 23362 7 15 (DEP,23362003) Delayed neutron yield . 23362 7 16 (SPSDD,23357009) Superseded by newer publication 23362 7 17 1972, in German, data are different. 23362 7 18 ENDBIB 16 0 23362 7 19 COMMON 2 3 23362 7 20 EN-NRM ASSUM 23362 7 21 EV PC/FIS 23362 7 22 0.0253 2.4 23362 7 23 ENDCOMMON 3 0 23362 7 24 DATA 2 1 23362 7 25 DATA DATA-ERR 23362 7 26 NO-DIM NO-DIM 23362 7 27 2.4E-2 0.1E-2 23362 7 28 ENDDATA 3 0 23362 7 29 ENDSUBENT 28 0 23362 799999 SUBENT 23362008 20171020 226823362 8 1 BIB 7 16 23362 8 2 REACTION (35-BR-88(0,B-)36-KR-88,,PN) 23362 8 3 REL-REF (A,41617003,P.M.Aron+,J,SJA,16,447,1964) 23362 8 4 Engl.translation of: 23362 8 5 (A,41617003,P.M.Aron+,J,AE,16,368,1964) 23362 8 6 6.0+-1.6 % 23362 8 7 ANALYSIS - Neutron emission probabilities were derived by 23362 8 8 dividing the neutron yields by the cumulative fission 23362 8 9 yields of the precursor. 23362 8 10 ASSUMED (ASSUM,92-U-235(N,F)35-BR-88,CUM,FY) 23362 8 11 DECAY-DATA (35-BR-88,16.3SEC) 23362 8 12 ERR-ANALYS (DATA-ERR) Type of error is not explained in the 23362 8 13 article 23362 8 14 STATUS (TABLE) Table IV of Conf.Proc. 69VIENNA,,591,1969 23362 8 15 (DEP,23362003) Delayed neutron yield . 23362 8 16 (SPSDD,23357010) Superseded by newer publication 23362 8 17 1972, in German, data are little different. 23362 8 18 ENDBIB 16 0 23362 8 19 COMMON 2 3 23362 8 20 EN-NRM ASSUM 23362 8 21 EV PC/FIS 23362 8 22 0.0253 3.0 23362 8 23 ENDCOMMON 3 0 23362 8 24 DATA 2 1 23362 8 25 DATA DATA-ERR 23362 8 26 NO-DIM NO-DIM 23362 8 27 4.0E-2 0.5E-2 23362 8 28 ENDDATA 3 0 23362 8 29 ENDSUBENT 28 0 23362 899999 SUBENT 23362009 20171020 226823362 9 1 BIB 7 16 23362 9 2 REACTION (35-BR-89(0,B-)36-KR-89,,PN) 23362 9 3 REL-REF (A,41617004,P.M.Aron+,J,SJA,16,447,1964) 23362 9 4 Engl.translation of: 23362 9 5 (A,41617004,P.M.Aron+,J,AE,16,368,1964) 23362 9 6 7.+-2. % 23362 9 7 ANALYSIS - Neutron emission probabilities were derived by 23362 9 8 dividing the neutron yields by the cumulative fission 23362 9 9 yields of the precursor. 23362 9 10 ASSUMED (ASSUM,92-U-235(N,F)35-BR-89,CUM,FY) 23362 9 11 DECAY-DATA (35-BR-89,4.4SEC) 23362 9 12 ERR-ANALYS (DATA-ERR) Type of error is not explained in the 23362 9 13 article 23362 9 14 STATUS (TABLE) Table IV of Conf.Proc. 69VIENNA,,591,1969 23362 9 15 (DEP,23362003) Delayed neutron yield . 23362 9 16 (SPSDD,23357011) Superseded by newer publication 23362 9 17 1972, in German, data are different. 23362 9 18 ENDBIB 16 0 23362 9 19 COMMON 2 3 23362 9 20 EN-NRM ASSUM 23362 9 21 EV PC/FIS 23362 9 22 0.0253 2.7 23362 9 23 ENDCOMMON 3 0 23362 9 24 DATA 2 1 23362 9 25 DATA DATA-ERR 23362 9 26 NO-DIM NO-DIM 23362 9 27 6.7E-2 1.6E-2 23362 9 28 ENDDATA 3 0 23362 9 29 ENDSUBENT 28 0 23362 999999 SUBENT 23362010 20171020 226823362 10 1 BIB 6 12 23362 10 2 REACTION (35-BR-90(0,B-)36-KR-90,,PN) 23362 10 3 ANALYSIS - Neutron emission probabilities were derived by 23362 10 4 dividing the neutron yields by the cumulative fission 23362 10 5 yields of the precursor. 23362 10 6 ASSUMED (ASSUM,92-U-235(N,F)35-BR-90,CUM,FY) 23362 10 7 DECAY-DATA (35-BR-90,1.6SEC) 23362 10 8 ERR-ANALYS (DATA-ERR) Type of error is not explained in the 23362 10 9 article 23362 10 10 STATUS (TABLE) Table IV of Conf.Proc. 69VIENNA,,591,1969 23362 10 11 (DEP,23362003) Delayed neutron yield . 23362 10 12 (SPSDD,23357012) Superseded by newer publication 23362 10 13 1972, in German, data are little different. 23362 10 14 ENDBIB 12 0 23362 10 15 COMMON 2 3 23362 10 16 EN-NRM ASSUM 23362 10 17 EV PC/FIS 23362 10 18 0.0253 1.4 23362 10 19 ENDCOMMON 3 0 23362 10 20 DATA 2 1 23362 10 21 DATA DATA-ERR 23362 10 22 NO-DIM NO-DIM 23362 10 23 10.4E-2 2.5E-2 23362 10 24 ENDDATA 3 0 23362 10 25 ENDSUBENT 24 0 23362 1099999 SUBENT 23362011 20171020 226823362 11 1 BIB 6 12 23362 11 2 REACTION (35-BR-91(0,B-)36-KR-91,,PN) 23362 11 3 ANALYSIS Br-91 HL was defined from neutron decay curves to be 23362 11 4 ~0.5sec. 23362 11 5 - Neutron emission probabilities were derived by 23362 11 6 dividing the neutron yields by the cumulative fission 23362 11 7 yields of the precursor. 23362 11 8 ASSUMED (ASSUM,92-U-235(N,F)35-BR-91,CUM,FY) 23362 11 9 DECAY-DATA (35-BR-91,0.5SEC) 23362 11 10 ERR-ANALYS (DATA-ERR) Type of error is not explained in the 23362 11 11 article 23362 11 12 STATUS (TABLE) Table IV of Conf.Proc. 69VIENNA,,591,1969 23362 11 13 (DEP,23362003) Delayed neutron yield . 23362 11 14 ENDBIB 12 0 23362 11 15 COMMON 2 3 23362 11 16 EN-NRM ASSUM 23362 11 17 EV PC/FIS 23362 11 18 0.0253 0.4 23362 11 19 ENDCOMMON 3 0 23362 11 20 DATA 2 1 23362 11 21 DATA DATA-ERR 23362 11 22 NO-DIM NO-DIM 23362 11 23 4.5E-2 1.8E-2 23362 11 24 ENDDATA 3 0 23362 11 25 ENDSUBENT 24 0 23362 1199999 SUBENT 23362012 20171020 226823362 12 1 BIB 7 19 23362 12 2 REACTION (37-RB-93(0,B-)38-SR-93,,PN) 23362 12 3 REL-REF (A,23360003,I.Amarel+,J,JIN,31,577,1969) 1.43+-0.18 % 23362 12 4 (A,,S.Amiel+,C,67VIENNA,,115,1967) 2.6+-0.4 % 23362 12 5 (A,,W.L.Talbert Jr+,J,PR,177,1805,1969) 1.59+-0.29 % 23362 12 6 (R,,I.Chaumont+,W,CHAUMONT,1969) Mentioned in the 23362 12 7 article as "to be published" 23362 12 8 ANALYSIS Rb-93 HL was defined from neutron decay curve to be 23362 12 9 ~5.9 sec 23362 12 10 - Neutron emission probabilities were derived by 23362 12 11 dividing the neutron yields by the cumulative fission 23362 12 12 yields of the precursor. 23362 12 13 ASSUMED (ASSUM,92-U-235(N,F)37-RB-93,CUM,FY) From I.Chamont+ 23362 12 14 DECAY-DATA (37-RB-93,6.2SEC) 23362 12 15 ERR-ANALYS (DATA-ERR) Type of error is not explained in the 23362 12 16 article 23362 12 17 STATUS (TABLE) Table IV of Conf.Proc. 69VIENNA,,591,1969 23362 12 18 (DEP,23362003) Delayed neutron yield . 23362 12 19 (SPSDD,23357013) Superseded by newer publication 23362 12 20 1972, in German, data are little different. 23362 12 21 ENDBIB 19 0 23362 12 22 COMMON 2 3 23362 12 23 EN-NRM ASSUM 23362 12 24 EV PC/FIS 23362 12 25 0.0253 2.97 23362 12 26 ENDCOMMON 3 0 23362 12 27 DATA 2 1 23362 12 28 DATA DATA-ERR 23362 12 29 NO-DIM NO-DIM 23362 12 30 2.2E-2 0.6E-2 23362 12 31 ENDDATA 3 0 23362 12 32 ENDSUBENT 31 0 23362 1299999 SUBENT 23362013 20171020 226823362 13 1 BIB 7 15 23362 13 2 REACTION (37-RB-94(0,B-)38-SR-94,,PN) 23362 13 3 REL-REF (A,23360013,I.Amarel+,J,JIN,31,577,1969) 11.25+-1.46 % 23362 13 4 ANALYSIS Rb-94 HL was defined from neutron decay curves to be 23362 13 5 ~2.3sec. 23362 13 6 - Neutron emission probabilities were derived by 23362 13 7 dividing the neutron yields by the cumulative fission 23362 13 8 yields of the precursor. 23362 13 9 ASSUMED (ASSUM,92-U-235(N,F)37-RB-94,CUM,FY) 23362 13 10 DECAY-DATA (37-RB-94,2.3SEC) 23362 13 11 ERR-ANALYS (DATA-ERR) Type of error is not explained in the 23362 13 12 article 23362 13 13 STATUS (TABLE) Table IV of Conf.Proc. 69VIENNA,,591,1969 23362 13 14 (DEP,23362003) Delayed neutron yield . 23362 13 15 (SPSDD,23357014) Superseded by newer publication 23362 13 16 1972, in German, data are little different. 23362 13 17 ENDBIB 15 0 23362 13 18 COMMON 2 3 23362 13 19 EN-NRM ASSUM 23362 13 20 EV PC/FIS 23362 13 21 0.0253 1.52 23362 13 22 ENDCOMMON 3 0 23362 13 23 DATA 2 1 23362 13 24 DATA DATA-ERR 23362 13 25 NO-DIM NO-DIM 23362 13 26 11.1E-2 2.3E-2 23362 13 27 ENDDATA 3 0 23362 13 28 ENDSUBENT 27 0 23362 1399999 SUBENT 23362014 20171020 226823362 14 1 BIB 6 10 23362 14 2 REACTION (39-Y-98(0,B-)40-ZR-98,,PN) 23362 14 3 ANALYSIS - Neutron emission probabilities were derived by 23362 14 4 dividing the neutron yields by the cumulative fission 23362 14 5 yields of the precursor. 23362 14 6 ASSUMED (ASSUM,92-U-235(N,F)39-Y-98,CUM,FY) 23362 14 7 DECAY-DATA (39-Y-98,2.3SEC) 23362 14 8 ERR-ANALYS (DATA-ERR) Type of error is not explained in the 23362 14 9 article 23362 14 10 STATUS (TABLE) Table IV of Conf.Proc. 69VIENNA,,591,1969 23362 14 11 (DEP,23362003) Delayed neutron yield . 23362 14 12 ENDBIB 10 0 23362 14 13 COMMON 2 3 23362 14 14 EN-NRM ASSUM 23362 14 15 EV PC/FIS 23362 14 16 0.0253 2.4 23362 14 17 ENDCOMMON 3 0 23362 14 18 DATA 2 1 23362 14 19 DATA DATA-ERR 23362 14 20 NO-DIM NO-DIM 23362 14 21 0.7E-2 0.4E-2 23362 14 22 ENDDATA 3 0 23362 14 23 ENDSUBENT 22 0 23362 1499999 SUBENT 23362015 20171020 226823362 15 1 BIB 6 12 23362 15 2 REACTION (52-TE-136(0,B-)53-I-136,,PN) 23362 15 3 ANALYSIS Te-136 HL was defined by gamma-ray spectra to be 23362 15 4 20.9+-0.5 sec. 23362 15 5 - Neutron emission probabilities were derived by 23362 15 6 dividing the neutron yields by the cumulative fission 23362 15 7 yields of the precursor. 23362 15 8 ASSUMED (ASSUM,92-U-235(N,F)52-TE-136,CUM,FY) 23362 15 9 DECAY-DATA (52-TE-136,20.SEC) 23362 15 10 ADD-RES Te-135 HL was determined from gamma-ray spectra to be 23362 15 11 16.6+-0.9 sec 23362 15 12 STATUS (TABLE) Table IV of Conf.Proc. 69VIENNA,,591,1969 23362 15 13 (DEP,23362003) Delayed neutron yield . 23362 15 14 ENDBIB 12 0 23362 15 15 COMMON 2 3 23362 15 16 EN-NRM ASSUM 23362 15 17 EV PC/FIS 23362 15 18 0.0253 2.2 23362 15 19 ENDCOMMON 3 0 23362 15 20 DATA 1 1 23362 15 21 DATA-APRX 23362 15 22 NO-DIM 23362 15 23 0.5E-2 23362 15 24 ENDDATA 3 0 23362 15 25 ENDSUBENT 24 0 23362 1599999 SUBENT 23362016 20171020 226823362 16 1 BIB 5 11 23362 16 2 REACTION (52-TE-137(0,B-)53-I-137,,PN) 23362 16 3 ANALYSIS Te-137 HL was defined from neutron decay curves and 23362 16 4 gamma-ray spectra to be ~3.5sec, from neutron decay 23362 16 5 curve for counted I-137 - 3.5+-0.5 sec. 23362 16 6 - Neutron emission probabilities were derived by 23362 16 7 dividing the neutron yields by the cumulative fission 23362 16 8 yields of the precursor. 23362 16 9 ASSUMED (ASSUM,92-U-235(N,F)52-TE-137,CUM,FY) 23362 16 10 DECAY-DATA (52-TE-137,3.5SEC) 23362 16 11 STATUS (TABLE) Table IV of Conf.Proc.69VIENNA,,591,1969 23362 16 12 (DEP,23362003) Delayed neutron yield . 23362 16 13 ENDBIB 11 0 23362 16 14 COMMON 2 3 23362 16 15 EN-NRM ASSUM 23362 16 16 EV PC/FIS 23362 16 17 0.0253 1.2 23362 16 18 ENDCOMMON 3 0 23362 16 19 DATA 1 1 23362 16 20 DATA-APRX 23362 16 21 NO-DIM 23362 16 22 0.5E-2 23362 16 23 ENDDATA 3 0 23362 16 24 ENDSUBENT 23 0 23362 1699999 SUBENT 23362017 20171020 226823362 17 1 BIB 7 17 23362 17 2 REACTION (53-I-137(0,B-)54-XE-137,,PN) 23362 17 3 REL-REF (D,41617005,P.M.Aron+,J,SJA,16,447,1964) 23362 17 4 Engl.translation of: 23362 17 5 (D,41617005,P.M.Aron+,J,AE,16,368,1964) 23362 17 6 3.+-0.5 % 23362 17 7 ANALYSIS - Neutron emission probabilities were derived by 23362 17 8 dividing the neutron yields by the cumulative fission 23362 17 9 yields of the precursor. 23362 17 10 ASSUMED (ASSUM,92-U-235(N,F)53-I-137,CUM,FY) 23362 17 11 DECAY-DATA (53-I-137,24.4SEC) 23362 17 12 ERR-ANALYS (DATA-ERR) Type of error is not explained in the 23362 17 13 article 23362 17 14 STATUS (TABLE) Table IV of Conf.Proc. 69VIENNA,,591,1969 23362 17 15 (DEP,23362003) Delayed neutron yield . 23362 17 16 (COREL,23362018) Direct measurement 23362 17 17 (SPSDD,23357016) Newer publication (1972, in German), 23362 17 18 data valuse are the same 23362 17 19 ENDBIB 17 0 23362 17 20 COMMON 2 3 23362 17 21 EN-NRM ASSUM 23362 17 22 EV PC/FIS 23362 17 23 0.0253 4.2 23362 17 24 ENDCOMMON 3 0 23362 17 25 DATA 2 1 23362 17 26 DATA DATA-ERR 23362 17 27 NO-DIM NO-DIM 23362 17 28 5.2E-2 0.5E-2 23362 17 29 ENDDATA 3 0 23362 17 30 ENDSUBENT 29 0 23362 1799999 SUBENT 23362018 20171020 226823362 18 1 BIB 6 11 23362 18 2 REACTION (53-I-137(0,B-)54-XE-137,,PN) 23362 18 3 REL-REF (A,41617005,P.M.Aron+,J,SJA,16,447,1964) 23362 18 4 Engl.translation of: 23362 18 5 (A,41617005,P.M.Aron+,J,AE,16,368,1964) 23362 18 6 3.+-0.5 % 23362 18 7 ANALYSIS Direct measurement. 23362 18 8 DECAY-DATA (53-I-137,24.4SEC) 23362 18 9 ERR-ANALYS (DATA-ERR) Type of error is not explained in the 23362 18 10 article 23362 18 11 STATUS (TABLE) Table IV of Conf.Proc. 69VIENNA,,591,1969 23362 18 12 (COREL,23362017) Indirect measurement . 23362 18 13 ENDBIB 11 0 23362 18 14 NOCOMMON 0 0 3 23362 18 15 DATA 2 1 23362 18 16 DATA DATA-ERR 23362 18 17 NO-DIM NO-DIM 23362 18 18 4.7E-2 1.0E-2 23362 18 19 ENDDATA 3 0 23362 18 20 ENDSUBENT 19 0 23362 1899999 SUBENT 23362019 20171020 226823362 19 1 BIB 7 16 23362 19 2 REACTION (53-I-138(0,B-)54-XE-138,,PN) 23362 19 3 REL-REF (A,41617006,P.M.Aron+,J,SJA,16,447,1964) 23362 19 4 Engl.translation of: 23362 19 5 (A,41617006,P.M.Aron+,J,AE,16,368,1964) 23362 19 6 2.0+-0.5 % 23362 19 7 ANALYSIS - Neutron emission probabilities were derived by 23362 19 8 dividing the neutron yields by the cumulative fission 23362 19 9 yields of the precursor. 23362 19 10 ASSUMED (ASSUM,92-U-235(N,F)53-I-138,CUM,FY) 23362 19 11 DECAY-DATA (53-I-138,6.3SEC) 23362 19 12 ERR-ANALYS (DATA-ERR) Type of error is not explained in the 23362 19 13 article 23362 19 14 STATUS (TABLE) Table IV of Conf.Proc. 69VIENNA,,591,1969 23362 19 15 (DEP,23362003) Delayed neutron yield . 23362 19 16 (SPSDD,23357017) Superseded by newer publication 23362 19 17 1972, in German, data value little different 23362 19 18 ENDBIB 16 0 23362 19 19 COMMON 2 3 23362 19 20 EN-NRM ASSUM 23362 19 21 EV PC/FIS 23362 19 22 0.0253 2.4 23362 19 23 ENDCOMMON 3 0 23362 19 24 DATA 2 1 23362 19 25 DATA DATA-ERR 23362 19 26 NO-DIM NO-DIM 23362 19 27 3.3E-2 0.8E-2 23362 19 28 ENDDATA 3 0 23362 19 29 ENDSUBENT 28 0 23362 1999999 SUBENT 23362020 20171020 226823362 20 1 BIB 6 12 23362 20 2 REACTION (53-I-139(0,B-)54-XE-139,,PN) 23362 20 3 ANALYSIS - Neutron emission probabilities were derived by 23362 20 4 dividing the neutron yields by the cumulative fission 23362 20 5 yields of the precursor. 23362 20 6 ASSUMED (ASSUM,92-U-235(N,F)53-I-139,CUM,FY) 23362 20 7 DECAY-DATA (53-I-139,2.0SEC) 23362 20 8 ERR-ANALYS (DATA-ERR) Type of error is not explained in the 23362 20 9 article 23362 20 10 STATUS (TABLE) Table IV of Conf.Proc. 69VIENNA,,591,1969 23362 20 11 (DEP,23362003) Delayed neutron yield . 23362 20 12 (SPSDD,23357018) Superseded by newer publication 23362 20 13 1972, in German, data are little different. 23362 20 14 ENDBIB 12 0 23362 20 15 COMMON 2 3 23362 20 16 EN-NRM ASSUM 23362 20 17 EV PC/FIS 23362 20 18 0.0253 1.1 23362 20 19 ENDCOMMON 3 0 23362 20 20 DATA 2 1 23362 20 21 DATA DATA-ERR 23362 20 22 NO-DIM NO-DIM 23362 20 23 9.1E-2 2.0E-2 23362 20 24 ENDDATA 3 0 23362 20 25 ENDSUBENT 24 0 23362 2099999 SUBENT 23362021 20171020 226823362 21 1 BIB 6 14 23362 21 2 REACTION (53-I-140(0,B-)54-XE-140,,PN) 23362 21 3 ANALYSIS I-140 HL was defined from neutron decay curves to be 23362 21 4 0.8+-0.2 sec . 23362 21 5 - Neutron emission probabilities were derived by 23362 21 6 dividing the neutron yields by the cumulative fission 23362 21 7 yields of the precursor. 23362 21 8 ASSUMED (ASSUM,92-U-235(N,F)53-I-140,CUM,FY) 23362 21 9 DECAY-DATA (53-I-140,0.8SEC) 23362 21 10 ERR-ANALYS (DATA-ERR) Type of error is not explained in the 23362 21 11 article 23362 21 12 STATUS (TABLE) Table IV of Conf.Proc. 69VIENNA,,591,1969 23362 21 13 (DEP,23362003) Delayed neutron yield . 23362 21 14 (SPSDD,23357019) Superseded by newer publication 23362 21 15 1972, in German, data are different. 23362 21 16 ENDBIB 14 0 23362 21 17 COMMON 2 3 23362 21 18 EN-NRM ASSUM 23362 21 19 EV PC/FIS 23362 21 20 0.0253 0.2 23362 21 21 ENDCOMMON 3 0 23362 21 22 DATA 2 1 23362 21 23 DATA DATA-ERR 23362 21 24 NO-DIM NO-DIM 23362 21 25 34.E-2 18.E-2 23362 21 26 ENDDATA 3 0 23362 21 27 ENDSUBENT 26 0 23362 2199999 SUBENT 23362022 20171020 226823362 22 1 BIB 6 12 23362 22 2 REACTION (53-I-141(0,B-)54-XE-141,,PN) 23362 22 3 ANALYSIS I-141 HL was defined from neutron decay curves to be 23362 22 4 ~0.4 sec . 23362 22 5 - Neutron emission probabilities were derived by 23362 22 6 dividing the neutron yields by the cumulative fission 23362 22 7 yields of the precursor. 23362 22 8 ASSUMED (ASSUM,92-U-235(N,F)53-I-141,CUM,FY) 23362 22 9 DECAY-DATA (53-I-141,0.4SEC) 23362 22 10 ERR-ANALYS (DATA-ERR) Type of error is not explained in the 23362 22 11 article 23362 22 12 STATUS (TABLE) Table IV of Conf.Proc. 69VIENNA,,591,1969 23362 22 13 (DEP,23362003) Delayed neutron yield . 23362 22 14 ENDBIB 12 0 23362 22 15 COMMON 2 3 23362 22 16 EN-NRM ASSUM 23362 22 17 EV PC/FIS 23362 22 18 0.0253 0.02 23362 22 19 ENDCOMMON 3 0 23362 22 20 DATA 3 1 23362 22 21 DATA +DATA-ERR -DATA-ERR 23362 22 22 NO-DIM NO-DIM NO-DIM 23362 22 23 90.E-2 10.E-2 30.E-2 23362 22 24 ENDDATA 3 0 23362 22 25 ENDSUBENT 24 0 23362 2299999 SUBENT 23362023 20171020 226823362 23 1 BIB 6 14 23362 23 2 REACTION (92-U-235(N,F)ELEM/MASS,DL/CUM,NU) 23362 23 3 Delayed neutron yield for specific isotope 23362 23 4 DECAY-DATA ((1.)34-SE-87,5.9SEC) 23362 23 5 ((2.)34-SE-88,2.SEC) 23362 23 6 COMMENT Of compiler. Data for other isotope frpm this table are23362 23 7 in Subent 003. 23362 23 8 from this work, Tomlison and del Marmol . 23362 23 9 REL-REF (R,23349001,L.Tomlison+,J,JIN,30,1649,1968) 23362 23 10 (R,23350001,L.Tomlison+,J,JIN,30,1995,1968) 23362 23 11 (R,,P.del Marmol+,J,JIN,29,273,1967) 23362 23 12 ERR-ANALYS (DATA-ERR) Type of error is not explained in the 23362 23 13 article 23362 23 14 STATUS (TABLE) Tables III, IV of Conf.Proc. 69VIENNA,,591,196923362 23 15 (SPSDD,22047003) Superseded by 22047.003 23362 23 16 ENDBIB 14 0 23362 23 17 COMMON 1 3 23362 23 18 EN-DUMMY 23362 23 19 EV 23362 23 20 0.0253 23362 23 21 ENDCOMMON 3 0 23362 23 22 DATA 5 2 23362 23 23 ELEMENT MASS DATA DATA-ERR DECAY-FLAG 23362 23 24 NO-DIM NO-DIM PC/FIS PC/FIS NO-DIM 23362 23 25 34. 87. 0.34E-2 0.11E-2 1. 23362 23 26 34. 88. 0.32E-2 0.16E-2 2. 23362 23 27 ENDDATA 4 0 23362 23 28 ENDSUBENT 27 0 23362 2399999 ENDENTRY 23 0 2336299999999