ENTRY 21306 20200118 22852130600000001 SUBENT 21306001 20200118 22852130600100001 BIB 17 48 2130600100002 TITLE Fission product yields in U-238 fission by Cf-252 2130600100003 neutrons 2130600100004 AUTHOR (K.Debertin) 2130600100005 INSTITUTE (2GERPTB) 2130600100006 REFERENCE (C,78HARWELL,,229,1978) 2130600100007 SAMPLE (92-U-238,ENR=0.93) Metallic uranium samples, 10 mm in 2130600100008 diam. and a thickness of 0.2 mm. 2130600100009 The U-238 samples had a 0.22% content of U-235. 2130600100010 the U-235 samples were enriched to 93% U-235. 2130600100011 MONITOR ((MONIT)92-U-238(N,F)56-BA-140,CUM,FY,,FIS) 2130600100012 MONIT-REF (,E.A.C.Crouch,J,AND,19,417,1977) 2130600100013 235U(nth,f) yields and 238U(n,f)140Ba yield 2130600100014 METHOD (ACTIV) 2130600100015 INC-SOURCE (CF252) A Cf-252 spont. fission neutron source 2130600100016 with about 1.5E+9 neutrons/sec. 2130600100017 INC-SPECT Cf-252 spont. fission neutron source and for 2130600100018 the monitor reaction a fission neutron spectrum. 2130600100019 DETECTOR (GELI) A 70 cm3 Ge(Li)-detector. 2130600100020 DECAY-DATA (38-SR-92,2.60HR) 2130600100021 (40-ZR-95,64.1D,DG,724.2,0.440, 2130600100022 DG,756.7,0.543) 2130600100023 (42-MO-99,2.790D,DG,739.5,0.1235) 2130600100024 (44-RU-103,39.28D,DG,497.1,0.909) 2130600100025 (53-I-131,8.02D,DG,364.5,0.816, 2130600100026 DG,637.0,0.0712) 2130600100027 (52-TE-132,3.205D) 2130600100028 (53-I-132,,DG,522.7,0.1593, 2130600100029 DG,630.2,0.1383, 2130600100030 DG,667.7,0.9894, 2130600100031 DG,772.6,0.751, 2130600100032 DG,954.6,0.1696) 2130600100033 (57-LA-140,1.678D,DG,328.8,0.2074, 2130600100034 DG,487.0,0.4594, 2130600100035 DG,815.9,0.2364) 2130600100036 DECAY-MON (56-BA-140,12.75D,DG,537.3,0.2439) 2130600100037 CORRECTION The following corrections have been made, 2130600100038 -dead-time and pile-up losses (0.3 to 6%), 2130600100039 -coincidence summing (0 to 7%), 2130600100040 -self-absorption of gamma-rays in the sample(1 to 18%)2130600100041 ERR-ANALYS Uncertainties are quoted at the 68% 2130600100042 confidence level. 2130600100043 STATUS (TABLE) Tbl.2 from 78HARWELL,,229,1978 2130600100044 HISTORY (19800130C) CN. 2130600100045 (20200118A) SD:Updated to new date formats,lower case. 2130600100046 FACILITY, INC SOURCE moved to Subents 002, 003. 2130600100047 EN-DUMMY -> KT-DUMMY; value changed (1.5 -> 1.42 MeV). 2130600100048 SF5=CHN -> CUM in MONITOR code. INC-SOURCE, INC-SPECT, 2130600100049 DECAY-DATA added. 140-Ba decay data moved to DECAY-MON.2130600100050 ENDBIB 48 0 2130600100051 COMMON 3 3 2130600100052 KT-DUMMY MONIT MONIT-ERR 2130600100053 MEV PC/FIS PC/FIS 2130600100054 1.42 6.05 0.13 2130600100055 ENDCOMMON 3 0 2130600100056 ENDSUBENT 55 0 2130600199999 SUBENT 21306002 20200118 22852130600200001 BIB 6 14 2130600200002 REACTION (92-U-238(N,F)MASS,CHN,FY,,FIS) 2130600200003 ANALYSIS Yields have been determined relative to the chain 2130600200004 yield of mass 140 given in monitor reference. 2130600200005 Cumulative yield=chain yield assumed. 2130600200006 CORRECTION Correction for fast fission of U-235 applied ( <1% ) 2130600200007 ERR-ANALYS (DATA-ERR) Errors comprise statistical uncertainties 2130600200008 and uncertainties in full energy peak efficiency, in 2130600200009 gamma-ray emission probability per decay and in the 2130600200010 correction factors. 2130600200011 238U(n,f)140Ba yield uncertainty (0.13) is not included2130600200012 STATUS (COREL,21306003) Yield derived from 238U(n,f) 2130600200013 235U(n-th,f) R-value 2130600200014 HISTORY (20200118A) SD: SF4=MASS added to REACTION code. 2130600200015 STATUS updated. 2130600200016 ENDBIB 14 0 2130600200017 NOCOMMON 0 0 2130600200018 DATA 3 19 2130600200019 MASS DATA DATA-ERR 2130600200020 NO-DIM PC/FIS PC/FIS 2130600200021 88. 2.38 0.17 2130600200022 91. 4.16 0.17 2130600200023 92. 4.68 0.50 2130600200024 95. 5.30 0.09 2130600200025 97. 5.81 0.13 2130600200026 99. 6.64 0.10 2130600200027 103. 6.25 0.09 2130600200028 105. 3.87 0.10 2130600200029 127. 0.175 0.012 2130600200030 129. 0.67 0.10 2130600200031 131. 3.41 0.06 2130600200032 132. 5.32 0.10 2130600200033 133. 6.98 0.16 2130600200034 135. 7.34 0.17 2130600200035 138. 6.84 0.45 2130600200036 142. 4.26 0.24 2130600200037 143. 4.73 0.23 2130600200038 147. 2.43 0.16 2130600200039 151. 0.80 0.04 2130600200040 ENDDATA 21 0 2130600200041 ENDSUBENT 40 0 2130600299999 SUBENT 21306003 20200118 22852130600300001 BIB 8 19 2130600300002 REACTION (92-U-238(N,F)MASS,CHN,FY,,FIS) 2130600300003 FACILITY (REAC,2GERPTB) FMRB reactor for thermal neutron 2130600300004 irradiation 2130600300005 METHOD (RVAL) The yields have been measured relative to the 2130600300006 U-235 thermal yields and normalized to the chain yield 2130600300007 of mass number 140 in fast neutron fission of U-238. 2130600300008 ANALYSIS Derived from 238U(n,f)-235U(nth,f) R-value. 2130600300009 Cumulative yield=chain yield assumed 2130600300010 MONITOR Data taken from the REL-REF and measured with thermal 2130600300011 neutrons from the reactor (see EN-NRM, no data given 2130600300012 in text). Additional experiment was made using reactor 2130600300013 for MONITOR (see METHOD). 2130600300014 ERR-ANALYS (DATA-ERR) Errors include statistical uncertainties 2130600300015 and uncertainties in the monitor yields. 2130600300016 238U(n,f)140Ba yield uncertainty (0.13) is not included2130600300017 STATUS (COREL,21306002) Yield normalized with 238U(n,f)140Ba 2130600300018 HISTORY (20200118A) SD: SF4=MASS added to REACTION code. 2130600300019 INC-SOURCE, INC-SPECT added. STATUS updated. 2130600300020 MONIT moved to Subent 001. 2130600300021 ENDBIB 19 0 2130600300022 COMMON 1 3 2130600300023 EN-NRM 2130600300024 EV 2130600300025 2.53E-02 2130600300026 ENDCOMMON 3 0 2130600300027 DATA 3 19 2130600300028 MASS DATA DATA-ERR 2130600300029 NO-DIM PC/FIS PC/FIS 2130600300030 88. 2.38 0.13 2130600300031 91. 3.98 0.13 2130600300032 92. 4.37 0.16 2130600300033 95. 5.16 0.13 2130600300034 97. 5.71 0.18 2130600300035 99. 6.49 0.17 2130600300036 103. 6.30 0.43 2130600300037 105. 4.06 0.19 2130600300038 127. 0.164 0.021 2130600300039 129. 0.49 0.13 2130600300040 131. 3.18 0.08 2130600300041 132. 5.14 0.11 2130600300042 133. 6.74 0.24 2130600300043 135. 7.35 0.22 2130600300044 138. 6.55 0.49 2130600300045 142. 4.60 0.17 2130600300046 143. 4.64 0.10 2130600300047 147. 2.68 0.15 2130600300048 151. 0.09 0.05 2130600300049 ENDDATA 21 0 2130600300050 ENDSUBENT 49 0 2130600399999 ENDENTRY 3 0 2130699999999