ENTRY 14537 20190625 14551453700000001 SUBENT 14537001 20190625 14551453700100001 BIB 11 33 1453700100002 TITLE Fission product data measured at Los Alamos for 1453700100003 fission spectrum and thermal neutrons on 239Pu, 235U, 1453700100004 238U 1453700100005 AUTHOR (H.D.Selby,M.R.Mac Innes,D.W.Barr,A.L.Keksis, 1453700100006 R.A.Meade, C.J.Burns,M.B.Chadwick,T.C.Wallstrom) 1453700100007 INSTITUTE (1USALAS) 1453700100008 REFERENCE (J,NDS,111,2891,2010) 1453700100009 #doi:10.1016/j.nds.2010.11.002 1453700100010 #NSR: 2010SE15 1453700100011 FACILITY (CRASS,1USALAS) BIG TEN critical assembly. The peak of1453700100012 the neutron energy spectrum was approximately 300 keV, 1453700100013 the average energy was approximately 600 keV. External 1453700100014 ion chambers and 235U-sealed fission chambers external 1453700100015 to the assembly were used to provide highly redundant 1453700100016 power-flux level time history monitoring during all 1453700100017 irradiations. 1453700100018 (REAC,1USALAS) The Omega West Reactor. 1453700100019 INC-SOURCE (THCOL) The irradiations were conducted in the thermal 1453700100020 column of OWR, that corresponded to a Cd ratio of 1453700100021 5,000-10,000, or a fully thermalized, isotropic source.1453700100022 METHOD (CHSEP) 1453700100023 CORRECTION Fission count data associated with the NIST fission 1453700100024 chamber was translated to absolute fission rates by 1453700100025 application of a number of corrections (dead-time loss,1453700100026 fission fragment loss, fissions in minor isotopes, 1453700100027 scattering and absorption). Cumulative corrections due 1453700100028 to these factors to the absolute fission rate ranged 1453700100029 from +-0.4% to +-0.8%. 1453700100030 ERR-ANALYS (DATA-ERR) Uncertainties assigned to the isotopic 1453700100031 masses of these reference deposits were evaluated at 1453700100032 +-1.5% to +-2%. 1453700100033 STATUS (TABLE) Data taken from Nucl.Data Sh.,111,2891,2010. 1453700100034 HISTORY (20190625C) OG. 1453700100035 ENDBIB 33 0 1453700100036 NOCOMMON 0 0 1453700100037 ENDSUBENT 36 0 1453700199999 SUBENT 14537002 20190625 14551453700200001 BIB 5 37 1453700200002 REACTION (((94-PU-239(N,F)ELEM/MASS,CUM,FY,,FST)/ 1453700200003 (94-PU-239(N,F)42-MO-99,CUM,FY,,FST))// 1453700200004 ((92-U-235(N,F)ELEM/MASS,CUM,FY,,MXW)/ 1453700200005 (92-U-235(N,F)42-MO-99,CUM,FY,,MXW))) 1453700200006 RESULT (RVAL) 1453700200007 INC-SPECT The average incident energy causing fission is about 1453700200008 1.3-1.5 MeV 1453700200009 SAMPLE BIG TEN irradiation materials 1453700200010 (94-PU-239,ENR=0.9911)+-0.0001 1453700200011 94-PU-238,ENR<0.00002 1453700200012 (94-PU-240,ENR=0.00880)+-0.00005 1453700200013 (94-PU-241,ENR=0.00010)+-0.00001 1453700200014 (94-PU-242,ENR=0.00005)+-0.00001 1453700200015 94-PU-244,ENR<0.00002 1453700200016 239Pu sample with 982.5 mg/g major element (+-0.5%). 1453700200017 The 239Pu foils were rolled, punched, weighed, and cold1453700200018 pressure welded into capsules of 0.177-mm thick 1453700200019 aluminum foil;all prepared in an Ar-filled glove box. 1453700200020 BIG TEN irradiation materials (reference foils) 1453700200021 (92-U-235,ENR=0.99912) 1453700200022 92-U-233,ENR<0.000001 1453700200023 (92-U-234,ENR=0.00029) 1453700200024 (92-U-236,ENR=0.000165) 1453700200025 (92-U-238,ENR=0.000414) 1453700200026 (94-PU-239,ENR=0.99978)+-0.00002 1453700200027 94-PU-238,ENR<0.000002 1453700200028 (94-PU-240,ENR=0.00021)+-0.00002 1453700200029 (94-PU-241,ENR=0.000005)+-0.000003 1453700200030 (94-PU-242,ENR=0.000005)+-0.000003 1453700200031 94-PU-244,ENR<0.000002 1453700200032 Reference foils 235U3O8 and 239PuO2 were prepared by 1453700200033 vapor deposition onto polished platinum disks. The 1453700200034 material was deposited using electron bombardment 1453700200035 heating for vaporization (about 2300 degrees C) with 1453700200036 condensation onto rotating substrates to enhance the 1453700200037 uniformity of deposit. 1453700200038 STATUS (TABLE) Table XV in Nucl.Data Sh.,111,2891,2010. 1453700200039 ENDBIB 37 0 1453700200040 COMMON 2 3 1453700200041 EN-DUM-NM EN-DUM-DN 1453700200042 MEV EV 1453700200043 1.4 0.0253 1453700200044 ENDCOMMON 3 0 1453700200045 DATA 4 8 1453700200046 MASS ELEMENT DATA DATA-ERR 1453700200047 NO-DIM NO-DIM NO-DIM PER-CENT 1453700200048 95. 40. 0.727 2.9 1453700200049 97. 40. 0.875 1.8 1453700200050 99. 42. 1. 1453700200051 137. 55. 1.030 1.8 1453700200052 140. 56. 0.836 1.0 1453700200053 143. 58. 0.726 3.9 1453700200054 144. 58. 0.659 2.9 1453700200055 147. 60. 0.916 0.8 1453700200056 ENDDATA 10 0 1453700200057 ENDSUBENT 56 0 1453700299999 SUBENT 14537003 20190625 14551453700300001 BIB 5 9 1453700300002 REACTION (94-PU-239(N,F)ELEM/MASS,CUM,FY,,FST) 1453700300003 MONITOR ((MONIT1)(94-PU-239(N,F)42-MO-99,CUM,FY,,FST)/ 1453700300004 (92-U-235(N,F)42-MO-99,CUM,FY,,MXW)) 1453700300005 ((MONIT2)92-U-235(N,F)ELEM/MASS,CUM,FY,,MXW) 1453700300006 MONIT-REF ((MONIT2),T.R.England+,3,ENDF/B-VI,9225,2001) 1453700300007 INC-SPECT The average incident energy causing fission is about 1453700300008 1.3-1.5 MeV 1453700300009 STATUS (TABLE) Table XV in Nucl.Data Sh.,111,2891,2010. 1453700300010 (DEP,14537002) R-value 1453700300011 ENDBIB 9 0 1453700300012 COMMON 3 3 1453700300013 EN-DUMMY MONIT1 MONIT1-ERR 1453700300014 MEV NO-DIM PER-CENT 1453700300015 1.4 1.015 2.0 1453700300016 ENDCOMMON 3 0 1453700300017 DATA 6 8 1453700300018 MASS ELEMENT DATA DATA-ERR MONIT2 MONIT2-ERR 1453700300019 NO-DIM NO-DIM PC/FIS PER-CENT PC/FIS PER-CENT 1453700300020 95. 40. 4.80 3.8 6.503 1.4 1453700300021 97. 40. 5.31 3.4 5.984 2.0 1453700300022 99. 42. 6.20 2.4 6.108 1.4 1453700300023 137. 55. 6.47 2.7 6.188 0.5 1453700300024 140. 56. 5.27 2.4 6.214 1.0 1453700300025 143. 58. 4.39 4.6 5.956 1.4 1453700300026 144. 58. 3.68 3.6 5.500 0.7 1453700300027 147. 60. 2.09 2.6 2.247 1.4 1453700300028 ENDDATA 10 0 1453700300029 ENDSUBENT 28 0 1453700399999 SUBENT 14537004 20190625 14551453700400001 BIB 5 35 1453700400002 REACTION (((92-U-235(N,F)ELEM/MASS,CUM,FY,,FST)/ 1453700400003 (92-U-235(N,F)42-MO-99,CUM,FY,,FST))// 1453700400004 ((92-U-235(N,F)ELEM/MASS,CUM,FY,,MXW)/ 1453700400005 (92-U-235(N,F)42-MO-99,CUM,FY,,MXW))) 1453700400006 RESULT (RVAL) 1453700400007 INC-SPECT The average incident energy causing fission is about 1453700400008 1.3-1.5 MeV 1453700400009 SAMPLE BIG TEN irradiation materials 1453700400010 (92-U-235,ENR=0.9989)+-0.0001 1453700400011 92-U-233,ENR<0.000005 1453700400012 (92-U-234,ENR=0.00035)+-0.00001 1453700400013 (92-U-236,ENR=0.00025)+-0.00001 1453700400014 (92-U-238,ENR=0.00053)+-0.00002 1453700400015 235U sample with 994.4 mg/g major element (+-0.5%). 1453700400016 The 235U foils were prepared by rolling to a nominal 1453700400017 thickness of 0.13 mm. Disks (12.7 mm-diameter) were 1453700400018 stamped from the rolled stock in air. The disk was then1453700400019 etched in nitric acid to remove oxide coating, rinsed 1453700400020 in alcohol, and placed in a argon-filled glovebox, 1453700400021 where they were weighed (foil mass 277.972 mg +-0.5%. 1453700400022 Foils were wrapped in 0.02-mm thick ultrapure (99.99%) 1453700400023 aluminum foil. 1453700400024 BIG TEN irradiation materials (reference foils) 1453700400025 (92-U-235,ENR=0.99912) 1453700400026 92-U-233,ENR<0.000001 1453700400027 (92-U-234,ENR=0.00029) 1453700400028 (92-U-236,ENR=0.000165) 1453700400029 (92-U-238,ENR=0.000414) 1453700400030 Reference foils 235U3O8 were prepared by vapor 1453700400031 deposition onto polished platinum disks. The material 1453700400032 was deposited using electron bombardment heating for 1453700400033 vaporization (about 2300 degrees C) with condensation 1453700400034 onto rotating substrates to enhance the uniformity of 1453700400035 deposit. 1453700400036 STATUS (TABLE) Table XV in Nucl.Data Sh.,111,2891,2010. 1453700400037 ENDBIB 35 0 1453700400038 COMMON 2 3 1453700400039 EN-DUM-NM EN-DUM-DN 1453700400040 MEV EV 1453700400041 1.4 0.0253 1453700400042 ENDCOMMON 3 0 1453700400043 DATA 4 6 1453700400044 MASS ELEMENT DATA DATA-ERR 1453700400045 NO-DIM NO-DIM NO-DIM PER-CENT 1453700400046 95. 40. 0.967 1.8 1453700400047 99. 42. 1. 1453700400048 137. 55. 1.003 1.2 1453700400049 140. 56. 0.953 0.5 1453700400050 144. 58. 0.909 2.3 1453700400051 147. 60. 0.976 0.5 1453700400052 ENDDATA 8 0 1453700400053 ENDSUBENT 52 0 1453700499999 SUBENT 14537005 20190625 14551453700500001 BIB 5 9 1453700500002 REACTION (92-U-235(N,F)ELEM/MASS,CUM,FY,,FST) 1453700500003 MONITOR ((MONIT1)(92-U-235(N,F)42-MO-99,CUM,FY,,FST)/ 1453700500004 (92-U-235(N,F)42-MO-99,CUM,FY,,MXW)) 1453700500005 ((MONIT2)92-U-235(N,F)ELEM/MASS,CUM,FY,,MXW) 1453700500006 MONIT-REF ((MONIT2),T.R.England+,3,ENDF/B-VI,9225,2001) 1453700500007 INC-SPECT The average incident energy causing fission is about 1453700500008 1.3-1.5 MeV 1453700500009 STATUS (TABLE) Table XV in Nucl.Data Sh.,111,2891,2010. 1453700500010 (DEP,14537004) R-value 1453700500011 ENDBIB 9 0 1453700500012 COMMON 3 3 1453700500013 EN-DUMMY MONIT1 MONIT1-ERR 1453700500014 MEV NO-DIM PER-CENT 1453700500015 1.4 0.9996 1.9 1453700500016 ENDCOMMON 3 0 1453700500017 DATA 6 6 1453700500018 MASS ELEMENT DATA DATA-ERR MONIT2 MONIT2-ERR 1453700500019 NO-DIM NO-DIM PC/FIS PER-CENT PC/FIS PER-CENT 1453700500020 95. 40. 6.30 3.0 6.503 1.4 1453700500021 99. 42. 6.11 2.4 6.108 1.4 1453700500022 137. 55. 6.20 2.3 6.188 0.5 1453700500023 140. 56. 5.91 2.2 6.214 1.0 1453700500024 144. 58. 5.00 3.2 5.500 0.7 1453700500025 147. 60. 2.19 2.4 2.247 1.4 1453700500026 ENDDATA 8 0 1453700500027 ENDSUBENT 26 0 1453700599999 SUBENT 14537006 20190625 14551453700600001 BIB 5 35 1453700600002 REACTION (((92-U-238(N,F)ELEM/MASS,CUM,FY,,FST)/ 1453700600003 (92-U-238(N,F)42-MO-99,CUM,FY,,FST))// 1453700600004 ((92-U-235(N,F)ELEM/MASS,CUM,FY,,MXW)/ 1453700600005 (92-U-235(N,F)42-MO-99,CUM,FY,,MXW))) 1453700600006 RESULT (RVAL) 1453700600007 INC-SPECT The average incident energy causing fission is about 1453700600008 1.3-1.5 MeV 1453700600009 SAMPLE BIG TEN irradiation materials 1453700600010 (92-U-238,ENR=0.99998)+-0.00001 1453700600011 92-U-233,ENR<0.000001 1453700600012 92-U-234,ENR<0.000001 1453700600013 (92-U-235,ENR=0.000015)+-0.000001 1453700600014 92-U-236,ENR<0.000001 1453700600015 238U sample with 994.8 mg/g major element (+-0.5%). 1453700600016 The 238U foils were prepared by rolling to a nominal 1453700600017 thickness of 0.13 mm. Disks (12.7 mm-diameter) were 1453700600018 stamped from the rolled stock in air. The disk was then1453700600019 etched in nitric acid to remove oxide coating, rinsed 1453700600020 in alcohol, and placed in a argon-filled glovebox, 1453700600021 where they were weighed (foil mass 304.007 mg +-0.5%. 1453700600022 Foils were wrapped in 0.02-mm thick ultrapure (99.99%) 1453700600023 aluminum foil. 1453700600024 BIG TEN irradiation materials (reference foils) 1453700600025 (92-U-235,ENR=0.99912) 1453700600026 92-U-233,ENR<0.000001 1453700600027 (92-U-234,ENR=0.00029) 1453700600028 (92-U-236,ENR=0.000165) 1453700600029 (92-U-238,ENR=0.000414) 1453700600030 Reference foils 235U3O8 were prepared by vapor 1453700600031 deposition onto polished platinum disks. The material 1453700600032 was deposited using electron bombardment heating for 1453700600033 vaporization (about 2300 degrees C) with condensation 1453700600034 onto rotating substrates to enhance the uniformity of 1453700600035 deposit. 1453700600036 STATUS (TABLE) Table XV in Nucl.Data Sh.,111,2891,2010. 1453700600037 ENDBIB 35 0 1453700600038 COMMON 2 3 1453700600039 EN-DUM-NM EN-DUM-DN 1453700600040 MEV EV 1453700600041 1.4 0.0253 1453700600042 ENDCOMMON 3 0 1453700600043 DATA 4 6 1453700600044 MASS ELEMENT DATA DATA-ERR 1453700600045 NO-DIM NO-DIM NO-DIM PER-CENT 1453700600046 95. 40. 0.752 2.8 1453700600047 99. 42. 1. 1453700600048 137. 55. 0.931 1.4 1453700600049 140. 56. 0.908 0.5 1453700600050 144. 58. 0.800 2.7 1453700600051 147. 60. 1.162 0.6 1453700600052 ENDDATA 8 0 1453700600053 ENDSUBENT 52 0 1453700699999 SUBENT 14537007 20190625 14551453700700001 BIB 5 9 1453700700002 REACTION (92-U-238(N,F)ELEM/MASS,CUM,FY,,FST) 1453700700003 MONITOR ((MONIT1)(92-U-238(N,F)42-MO-99,CUM,FY,,FST)/ 1453700700004 (92-U-235(N,F)42-MO-99,CUM,FY,,MXW)) 1453700700005 ((MONIT2)92-U-235(N,F)ELEM/MASS,CUM,FY,,MXW) 1453700700006 MONIT-REF ((MONIT2),T.R.England+,3,ENDF/B-VI,9225,2001) 1453700700007 INC-SPECT The average incident energy causing fission is about 1453700700008 1.3-1.5 MeV 1453700700009 STATUS (TABLE) Table XV in Nucl.Data Sh.,111,2891,2010. 1453700700010 (DEP,14537006) R-value 1453700700011 ENDBIB 9 0 1453700700012 COMMON 3 3 1453700700013 EN-DUMMY MONIT1 MONIT1-ERR 1453700700014 MEV NO-DIM PER-CENT 1453700700015 1.4 1.025 2.2 1453700700016 ENDCOMMON 3 0 1453700700017 DATA 6 6 1453700700018 MASS ELEMENT DATA DATA-ERR MONIT2 MONIT2-ERR 1453700700019 NO-DIM NO-DIM PC/FIS PER-CENT PC/FIS PER-CENT 1453700700020 95. 40. 5.01 3.8 6.503 1.4 1453700700021 99. 42. 6.26 2.6 6.108 1.4 1453700700022 137. 55. 5.91 2.7 6.188 0.5 1453700700023 140. 56. 5.78 2.5 6.214 1.0 1453700700024 144. 58. 4.51 3.4 5.500 0.7 1453700700025 147. 60. 2.68 2.7 2.247 1.4 1453700700026 ENDDATA 8 0 1453700700027 ENDSUBENT 26 0 1453700799999 SUBENT 14537008 20190625 14551453700800001 BIB 3 36 1453700800002 REACTION ((94-PU-239(N,F)ELEM/MASS,CUM,FY,,MXW)/ 1453700800003 (92-U-235(N,F)ELEM/MASS,CUM,FY,,MXW)) 1453700800004 SAMPLE OWR thermal irradiation materials 1453700800005 239Pu sample with mass 0.3748 mg +-1.5%, areal density 1453700800006 0.2951 mg/cm2. 1453700800007 (94-PU-239,ENR=0.99940) 1453700800008 94-PU-238,ENR<0.00007 1453700800009 (94-PU-240,ENR=0.00048) 1453700800010 94-PU-241,ENR<0.00001 1453700800011 94-PU-242,ENR<0.00007 1453700800012 Two 235U samples with mass 0.5085 mg +-1.5% and 1453700800013 0.5663 mg +-1.5% (areal densities in mg/cm2 0.4004 and 1453700800014 0.4459). 1453700800015 (92-U-235,ENR=0.9970) 1453700800016 (92-U-234,ENR=0.00069) 1453700800017 (92-U-236,ENR=0.00069) 1453700800018 (92-U-238,ENR=0.00159) 1453700800019 OWR thermal irradiation materials (reference foils) 1453700800020 (92-U-235,ENR=0.9970) 1453700800021 (92-U-234,ENR=0.00069) 1453700800022 (92-U-236,ENR=0.00069) 1453700800023 (92-U-238,ENR=0.00159) 1453700800024 (94-PU-239,ENR=0.99940) 1453700800025 94-PU-238,ENR<0.00007 1453700800026 (94-PU-240,ENR=0.00048) 1453700800027 94-PU-241,ENR<0.00001 1453700800028 94-PU-242,ENR<0.00007 1453700800029 The 235U reference foil was made by quantitatively 1453700800030 electroplating a solution containing about 100 ng of 1453700800031 235U (utilizing 232U tracer to determine chemical 1453700800032 yield). The 238U reference foil was made in a similar 1453700800033 manner from a solution containing about 10mu-g of 238U,1453700800034 also utilizing 232U tracer to determine chemical yield.1453700800035 The plutonium reference foil was electroplated from 1453700800036 a solution containing about 100 ng of 239Pu. 1453700800037 STATUS (TABLE) Table XVI in Nucl.Data Sh.,111,2891,2010. 1453700800038 ENDBIB 36 0 1453700800039 COMMON 1 3 1453700800040 EN-DUMMY 1453700800041 EV 1453700800042 0.0253 1453700800043 ENDCOMMON 3 0 1453700800044 DATA 4 2 1453700800045 MASS ELEMENT DATA DATA-ERR 1453700800046 NO-DIM NO-DIM NO-DIM PER-CENT 1453700800047 99. 42. 1.020 2.5 1453700800048 147. 60. 0.904 2.5 1453700800049 ENDDATA 4 0 1453700800050 ENDSUBENT 49 0 1453700899999 SUBENT 14537009 20190625 14551453700900001 BIB 4 5 1453700900002 REACTION (94-PU-239(N,F)ELEM/MASS,CUM,FY,,MXW) 1453700900003 MONITOR (92-U-235(N,F)ELEM/MASS,CUM,FY,,MXW) 1453700900004 MONIT-REF (,T.R.England+,3,ENDF/B-VI,9225,2001) 1453700900005 STATUS (TABLE) Table XVI in Nucl.Data Sh.,111,2891,2010. 1453700900006 (DEP,14537008) R-value 1453700900007 ENDBIB 5 0 1453700900008 COMMON 1 3 1453700900009 EN-DUMMY 1453700900010 EV 1453700900011 0.0253 1453700900012 ENDCOMMON 3 0 1453700900013 DATA 6 2 1453700900014 MASS ELEMENT DATA DATA-ERR MONIT MONIT-ERR 1453700900015 NO-DIM NO-DIM PC/FIS PER-CENT PC/FIS PER-CENT 1453700900016 99. 42. 6.23 2.9 6.108 1.4 1453700900017 147. 60. 2.03 2.9 2.247 1.4 1453700900018 ENDDATA 4 0 1453700900019 ENDSUBENT 18 0 1453700999999 ENDENTRY 9 0 1453799999999