ENTRY 21723 20161001 225321723 0 1 SUBENT 21723001 20161001 225321723 1 1 BIB 11 32 21723 1 2 INSTITUTE (2SWTWUR) Eidgenoessisches Institut fuer Reaktor- 21723 1 3 Forschung. 21723 1 4 REFERENCE (J,NSE,79,167,198110) - final publ. 21723 1 5 ((P,NEANDC(OR)-154,12,1980)=(P,INDC(SWT)-14,12,1980)) 21723 1 6 Abstract,data for Mo-99,Te-132. 21723 1 7 REL-REF (R,,J.K.Dickens+,J,NIM,175,535,1980) - decay-data 21723 1 8 of Mo-99 21723 1 9 (R,,J.K.Dickens+,J,NSE,73,42,1980) - decay-data of 21723 1 10 Sr-92, Y-93, Zr-97, Ba-139, Ba-140 21723 1 11 (R,,U.Reus+,R,GSI-79-2,1979) - decay-data of the rest 21723 1 12 of the products 21723 1 13 - G.Erdtmann and W.Soyka, 'Die gamma-Linien der 21723 1 14 Radionuklide,' Chemie, Mannheim, New York (1979). - 21723 1 15 decay-data of Cd-115m 21723 1 16 - 'A Handbook of Radioactivity Measurement Procedures,21723 1 17 NCRP Report No. 58, National Council on Radiation' 21723 1 18 Protection and Measurements (1978). - decay-data of 21723 1 19 Te-132, Ce-141, Ce-143, Sm-153 21723 1 20 AUTHOR (H.N.Erten,A.Gruetter,E.Roessler,H.R.von Gunten) 21723 1 21 TITLE Mass distribution in the reactor-neutron-induced 21723 1 22 fission of thorium-232 21723 1 23 FACILITY (REAC,2SWTWUR) Swimming pool reactor SAPHIR. 21723 1 24 INC-SOURCE (REAC) 21723 1 25 PART-DET (DG) Decay gammas of the fission products. 21723 1 26 ADD-RES (COMP) Comparison with literature both for reactor 21723 1 27 neutron and monoenergetic neutron induced fission 21723 1 28 of Th-232. 21723 1 29 CORRECTION .For Ag-113-m and Cd-115-m formation. 21723 1 30 HISTORY (19810119C) G.C. 21723 1 31 (19811201A) T.N - 002 was changed and 003 was added. 21723 1 32 (20161001A) SD:Updated to new date formats,lower case. 21723 1 33 Entry re-compiled. 21723 1 34 ENDBIB 32 0 21723 1 35 COMMON 1 3 21723 1 36 EN-DUMMY 21723 1 37 MEV 21723 1 38 3.3 21723 1 39 ENDCOMMON 3 0 21723 1 40 ENDSUBENT 39 0 21723 199999 SUBENT 21723002 20161001 225321723 2 1 BIB 13 42 21723 2 2 REACTION (90-TH-232(N,F)ELEM/MASS,CUM,FY,,FIS) 21723 2 3 MONITOR ((MONIT)90-TH-232(N,F)42-MO-99,CUM,FY,,FIS) 21723 2 4 (92-U-235(N,F)ELEM/MASS,CUM,FY,,FIS) 21723 2 5 MONIT-REF (,B.F.Rider,R,NEDO-12154-3B,1980)-The thermal-neutron 21723 2 6 -induced fission yields of U-238 used in the R method 21723 2 7 INC-SPECT Fission neutron spectrum. The thermal neutron flux was 21723 2 8 ~1.6 x 10**13 n/cm2/s and the fast neutron flux was 21723 2 9 ~3.3 x 10**12 ncm2/s. 21723 2 10 SAMPLE .Th-232 100%, Th(NO3)4.x H2O, 50 mg 21723 2 11 .U-235, 99.61%, UO2(NO3)2, 14.4 mu-g. 21723 2 12 The sources were wrapped in thin (~4 mg/cm2) aluminum 21723 2 13 foils and were placed in quartz tubes. 21723 2 14 Samples were irradiated simultaneously, but in 21723 2 15 separated positions, in the SAPHIR reactor for 1 h. 21723 2 16 METHOD (CHSEP) Radiochemical separation of the fission 21723 2 17 products from Th-232(n,f) and U-235(n,f). The 21723 2 18 quantity 21723 2 19 R=Ast(Th)*A2/(Ast(U)*A4) is measured, were 21723 2 20 Ast(Th)= activity of product in Th-232(n,f), 21723 2 21 A2= activity of Mo-99 in U-235(n,f), 21723 2 22 Ast(U)= activity of product in U-235(n,f), 21723 2 23 compilation by Rider(NEDO 12154-3B) was used.21723 2 24 A4= activity of Mo-99 in Th-232(n,f). 21723 2 25 The yields in thorium fission were then determined 21723 2 26 according to Yi(Th) = R*Yi(U)*Yst(Th)/Yst(U) 21723 2 27 (GSPEC) gamma-ray spectroscopy. 21723 2 28 DETECTOR (GELI ) Ge(Li) detectors. 45 cm3 and 54 cm3. 21723 2 29 Resolution about 2 keV at 1332 keV. 21723 2 30 (PROPC) Low background proportional counter for Sc-89, 21723 2 31 Y-90, and RU-106 counting. 21723 2 32 ANALYSIS Gaussian peak fit and decay analysis. 21723 2 33 ERR-ANALYS (ERR-T) Total error given, including the statistical 21723 2 34 error, the errors in the U-235 reference yields and 21723 2 35 (MONIT-ERR) Normalization uncertainty 21723 2 36 MISC-COL (MISC1) R-value Y1*Y2/(Y3-Y4) measured. 21723 2 37 (MISC2) Number of determinations. 21723 2 38 FLAG (1.) Values based on R-method are omitted. 21723 2 39 (2.) Determined by beta counting. 21723 2 40 (3.) Determined by direct gamma-ray spectroscopy. 21723 2 41 STATUS (TABLE) Data taken from Tbl.III,IV of NSE,79,167,1981 21723 2 42 (DEP,21723004) data for normalization 21723 2 43 HISTORY (20161001A) SD: BIB update. 21723 2 44 ENDBIB 42 0 21723 2 45 COMMON 4 3 21723 2 46 ELEM-NRM MASS-NRM MONIT MONIT-ERR 21723 2 47 NO-DIM NO-DIM PC/FIS PC/FIS 21723 2 48 42. 99. 2.98 0.15 21723 2 49 ENDCOMMON 3 0 21723 2 50 DATA 9 36 21723 2 51 ELEMENT MASS ISOMER DATA ERR-T MISC1 21723 2 52 MISC1-ERR MISC2 FLAG 21723 2 53 NO-DIM NO-DIM NO-DIM PC/FIS PC/FIS NO-DIM 21723 2 54 NO-DIM NO-DIM NO-DIM 21723 2 55 32. 77. 0. 0.0113 0.0017 21723 2 56 4. 1. 21723 2 57 32. 78. 0.073 0.011 21723 2 58 4. 1. 21723 2 59 35. 83. 2.13 0.20 8.0921723 2 60 0.61 3. 21723 2 61 35. 84. 3.84 0.31 8.1921723 2 62 0.64 3. 21723 2 63 38. 89. 7.50 0.54 3.1721723 2 64 0.15 5. 2. 21723 2 65 38. 90. 8.21 0.79 2.921723 2 66 0.23 2. 2. 21723 2 67 38. 91. 7.59 0.42 2.6121723 2 68 0.03 3. 21723 2 69 38. 92. 6.80 0.41 2.3521723 2 70 0.05 3. 21723 2 71 39. 93. 6.76 0.54 2.1621723 2 72 0.03 2. 21723 2 73 40. 95. 5.63 0.31 1.7621723 2 74 0.02 2. 3. 21723 2 75 40. 97. 4.50 0.35 1.5521723 2 76 0.08 2. 3. 21723 2 77 44. 103. 0.158 0.009 0.10621723 2 78 0.002 4. 21723 2 79 44. 105. 0.0561 0.0046 0.11821723 2 80 0.002 4. 21723 2 81 44. 106. 0.0487 0.0085 0.24721723 2 82 0.4 3. 2. 21723 2 83 46. 109. 0.0563 0.0096 3.4821723 2 84 0.08 5. 21723 2 85 46. 112. 0.0774 0.0042 12.1321723 2 86 0.15 5. 21723 2 87 47. 111. 0.0703 0.0056 7.521723 2 88 0.15 5. 21723 2 89 47. 113. 0. 0.0785 0.0079 11.6821723 2 90 0.35 5. 21723 2 91 48. 115. 0. 0.0506 0.0061 11.2121723 2 92 0.11 5. 21723 2 93 48. 117. 0. 0.050 0.012 12.9721723 2 94 0.2 5. 21723 2 95 48. 117. 1. 0.0227 0.0053 10.321723 2 96 0.46 5. 21723 2 97 51. 127. 0.0809 0.0078 1.3221723 2 98 0.02 4. 21723 2 99 51. 129. 0.310 0.025 0.84321723 2 100 0.008 4. 21723 2 101 52. 132. 3.16 0.17 1.521723 2 102 0.02 13. 21723 2 103 53. 131. 1.80 0.10 1.2721723 2 104 0.02 3. 21723 2 105 53. 134. 0. 6.23 0.56 1.6321723 2 106 0.07 3. 21723 2 107 53. 135. 6.14 0.36 1.9921723 2 108 0.03 3. 21723 2 109 56. 139. 7.11 0.42 2.2821723 2 110 0.05 3. 21723 2 111 56. 140. 8.12 0.45 2.6721723 2 112 0.03 3. 21723 2 113 58. 141. 7.36 0.47 2.5921723 2 114 0.09 4. 21723 2 115 58. 143. 6.96 0.46 2.3821723 2 116 0.09 4. 21723 2 117 58. 144. 7.79 0.49 2.9621723 2 118 0.09 4. 21723 2 119 60. 147. 3.05 0.20 2.7421723 2 120 0.11 4. 21723 2 121 61. 149. 1.16 0.07 2.1821723 2 122 0.06 4. 21723 2 123 61. 151. 0.396 0.03 1.9221723 2 124 0.1 4. 21723 2 125 62. 153. 0.106 0.012 1.3321723 2 126 0.13 3. 21723 2 127 ENDDATA 76 0 21723 2 128 ENDSUBENT 127 0 21723 299999 SUBENT 21723003 20161001 225321723 3 1 BIB 4 6 21723 3 2 REACTION (90-TH-232(N,F)48-CD-117,CUM,FY,,FIS) 21723 3 3 MISC-COL (MISC ) Number of determinations. 21723 3 4 ERR-ANALYS (ERR-T) Total error. See description in Subent 002 and 21723 3 5 STATUS in Subent 003. 21723 3 6 STATUS (TABLE) Data taken from Tbl.III of NSE,79,167,1981 21723 3 7 (DEP,21723002) Sum of values for Cd-117g and Cd-117m. 21723 3 8 ENDBIB 6 0 21723 3 9 NOCOMMON 0 0 21723 3 10 DATA 5 1 21723 3 11 ELEMENT MASS DATA ERR-T MISC 21723 3 12 NO-DIM NO-DIM PC/FIS PC/FIS NO-DIM 21723 3 13 48. 117. 0.073 0.017 5. 21723 3 14 ENDDATA 3 0 21723 3 15 ENDSUBENT 14 0 21723 399999 SUBENT 21723004 20161001 225321723 4 1 BIB 12 26 21723 4 2 REACTION (90-TH-232(N,F)ELEM/MASS,IND,FY,,FIS) 21723 4 3 DECAY-DATA (42-MO-99,66.0HR,DG) 21723 4 4 (52-TE-132,78.2HR,DG) 21723 4 5 INC-SPECT Fission neutrons. The irradiations lasted for ~70 h 21723 4 6 and the fission rate amounted to ~1400 fiss/s. 21723 4 7 SAMPLE Uniformly electroplated deposits of 6 cm diameter, 21723 4 8 containing about 15 mg of Th-232 21723 4 9 METHOD (CHSEP) The number of fissions is directly counted, 21723 4 10 Mo and Te are chemically separated and gamma-counted. 21723 4 11 DETECTOR (FISCH) Aluminium parallel plate type fission counter, 21723 4 12 (GELI) Ge(Li)-detectors, 45 cm3, resolution about 21723 4 13 2 keV at 1332 keV , and 54 cm3, resolution about 21723 4 14 2 keV at 1332. keV. 21723 4 15 ANALYSIS .Gaussian peak fit and decay analysis. 21723 4 16 COMMENT .Comparison with literature values. 21723 4 17 ERR-ANALYS (ERR-T) Total error given. It includes - 21723 4 18 (ERR-S) statistical error 21723 4 19 in fission fragment counting = 1% 21723 4 20 in activity measurements = 2% 21723 4 21 in chemical yields = 3% 21723 4 22 value in common section was estimated by compiler. 21723 4 23 (ERR-SYS) The total systematic error is 4% from uncer- 21723 4 24 tainties in decay schemes and detector efficiencies. 21723 4 25 MISC-COL (MISC) Number of experiments done. 21723 4 26 STATUS (TABLE) Data taken from from Tbl.I of NSE,79,167,1981 21723 4 27 HISTORY (20161001T) SD: Subent was added from 21712.002. 21723 4 28 ENDBIB 26 0 21723 4 29 COMMON 3 3 21723 4 30 ERR-S ERR-SYS MISC 21723 4 31 PER-CENT PER-CENT NO-DIM 21723 4 32 3.7 4. 10. 21723 4 33 ENDCOMMON 3 0 21723 4 34 DATA 4 2 21723 4 35 ELEMENT MASS DATA ERR-T 21723 4 36 NO-DIM NO-DIM PC/FIS PC/FIS 21723 4 37 42. 99. 2.98 0.15 21723 4 38 52. 132. 2.76 0.16 21723 4 39 ENDDATA 4 0 21723 4 40 ENDSUBENT 39 0 21723 499999 ENDENTRY 4 0 2172399999999