ENTRY 13134 20170724 14321313400000001 SUBENT 13134001 20170724 14321313400100001 BIB 14 46 1313400100002 TITLE The fission cross sections of 230Th, 232Th, 233U, 234U,1313400100003 236U, 238U, 237Np, 239Pu and 242Pu relative to 235U 1313400100004 at 14.74 MeV neutron energy 1313400100005 AUTHOR (J.W.Meadows) 1313400100006 INSTITUTE (1USAANL) 1313400100007 REFERENCE (J,ANE,15,421,1988) 1313400100008 (R,ANL-NDM-97,1986) Same data in table 1313400100009 (R,ANL-NDM-98,1987) Detailed error analysis 1313400100010 FACILITY (NGEN) Texas Nuclear Generator Model 9400 1313400100011 INC-SOURCE (D-T) 150+/-10 keVdeuterons on Ti-T target 1313400100012 INC-SPECT (EN-RSL-FW) Full-width-at-half-maximum 1313400100013 MONITOR 2(92-U-235(N,F),,SIG) 1313400100014 MONIT-REF 2(,,3,ENDF/B-V,,1978) 2.101 b +/- 6% 1313400100015 DETECTOR (FISCH) Low mass double ionization chamber 1313400100016 ERR-ANALYS Sources of uncertainties given include: 1313400100017 - counting statistics 1313400100018 - neutron energy 1313400100019 - thickness correction 1313400100020 - extrapolation correction 1313400100021 - alpha count 1313400100022 - isotopic analysis 1313400100023 - alpha half-lives 1313400100024 - thermal fission cross section ratios 1313400100025 - scattering correction. 1313400100026 The common uncertainties fully correlated with the 1313400100027 same combination tabulated in Table II of ANL/NDM-98 1313400100028 are provided as coded information in the COMMON 1313400100029 section data subentries. 1313400100030 COVARIANCE Correlation matrix between fission cross section ratios1313400100031 1 2 3 4 5 6 7 8 9 1313400100032 230Th/235U 1 100 1313400100033 232Th/235U 2 57 100 1313400100034 233U/235U 3 58 48 100 1313400100035 234U/235U 4 69 60 62 100 1313400100036 236U/235U 5 71 59 64 78 100 1313400100037 238U/235U 6 68 58 58 73 73 100 1313400100038 237Np/235U 7 53 51 41 53 53 56 100 1313400100039 239Pu/235U 8 52 43 50 59 62 59 36 100 1313400100040 242Pu/235U 9 42 40 37 44 43 39 37 35 100 1313400100041 STATUS (APRVD) J.W.Meadows, 1988/12/14. 1313400100042 (TABLE) Table 3 of Ann.Nucl.Energy 15(1988)421 1313400100043 HISTORY (19881110C) 1313400100044 (19900326U) BIB update 1313400100045 (20050926U) Format updated and second, third fourth 1313400100046 and fifth references added 1313400100047 (20170724A) On. Major revisions in 002-010. 1313400100048 ENDBIB 46 0 1313400100049 COMMON 1 3 1313400100050 MONIT 2 1313400100051 B 1313400100052 2.101 1313400100053 ENDCOMMON 3 0 1313400100054 ENDSUBENT 53 0 1313400199999 SUBENT 13134002 20170724 14321313400200001 BIB 4 9 1313400200002 REACTION 1((90-TH-230(N,F),,SIG)/(92-U-235(N,F),,SIG)) 1313400200003 2(90-TH-230(N,F),,SIG) 1313400200004 DECAY-DATA (90-TH-230,7.538E+4YR,A) 1313400200005 ERR-ANALYS (ERR-T) Total uncertainty 1313400200006 (ERR-1) Neutron energy 1313400200007 (ERR-3) Extrapolation correction 1313400200008 (ERR-4) Isotopic analysis of reaction sample 1313400200009 (ERR-5) Alpha-decay half-life of reaction sample 1313400200010 HISTORY (20170724A) On. ERR-ANALYS updated. 1313400200011 ENDBIB 9 0 1313400200012 COMMON 4 3 1313400200013 ERR-1 ERR-3 ERR-4 ERR-5 1313400200014 PER-CENT PER-CENT PER-CENT PER-CENT 1313400200015 1.00 0.30 0.00 0.39 1313400200016 ENDCOMMON 3 0 1313400200017 DATA 6 1 1313400200018 EN EN-ERR EN-RSL-FW DATA 1DATA 2ERR-T 1313400200019 MEV MEV MEV NO-DIM B PER-CENT 1313400200020 14.74 0.05 0.32 0.290 0.61 1.85 1313400200021 ENDDATA 3 0 1313400200022 ENDSUBENT 21 0 1313400299999 SUBENT 13134003 20170724 14321313400300001 BIB 4 14 1313400300002 REACTION 1((90-TH-232(N,F),,SIG)/(92-U-235(N,F),,SIG)) 1313400300003 2(90-TH-232(N,F),,SIG) 1313400300004 DECAY-DATA (90-TH-232,1.405E+10YR) 1313400300005 T1/2=1.405E+10 yr in INDC(NDS)-108 and Table IV of 1313400300006 ANL/NDM-97, but 1.405E+05 Table 2 of Ann.Nucl.Energy 1313400300007 15(1988)421. 1313400300008 ERR-ANALYS (ERR-T) Total uncertainty 1313400300009 (ERR-1) Neutron energy 1313400300010 (ERR-2) Thickness correction 1313400300011 (ERR-3) Extrapolation correction 1313400300012 (ERR-4) Isotopic analysis of reaction sample 1313400300013 (ERR-5) Alpha-decay half-life of reaction sample 1313400300014 (ERR-6) Prompt neutron scattering 1313400300015 HISTORY (20170724A) On. ERR-ANALYS updated. 1313400300016 ENDBIB 14 0 1313400300017 COMMON 6 3 1313400300018 ERR-1 ERR-2 ERR-3 ERR-4 ERR-5 ERR-6 1313400300019 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 1313400300020 1.00 0.30 0.30 0.40 0.39 0.67 1313400300021 ENDCOMMON 3 0 1313400300022 DATA 6 1 1313400300023 EN EN-ERR EN-RSL-FW DATA 1DATA 2ERR-T 1313400300024 MEV MEV MEV NO-DIM B PER-CENT 1313400300025 14.74 0.05 0.32 0.191 0.401 1.85 1313400300026 ENDDATA 3 0 1313400300027 ENDSUBENT 26 0 1313400399999 SUBENT 13134004 20170724 14321313400400001 BIB 4 8 1313400400002 REACTION 1((92-U-233(N,F),,SIG)/(92-U-235(N,F),,SIG)) 1313400400003 2(92-U-233(N,F),,SIG) 1313400400004 DECAY-DATA (92-U-233,1.592E+5YR,A) 1313400400005 ERR-ANALYS (ERR-T) Total uncertainty 1313400400006 (ERR-2) Thickness correction 1313400400007 (ERR-3) Extrapolation correction 1313400400008 (ERR-6) Prompt neutron scattering 1313400400009 HISTORY (20170724A) On. ERR-ANALYS updated. 1313400400010 ENDBIB 8 0 1313400400011 COMMON 3 3 1313400400012 ERR-2 ERR-3 ERR-6 1313400400013 PER-CENT PER-CENT PER-CENT 1313400400014 0.30 0.30 0.25 1313400400015 ENDCOMMON 3 0 1313400400016 DATA 6 1 1313400400017 EN EN-ERR EN-RSL-FW DATA 1DATA 2ERR-T 1313400400018 MEV MEV MEV NO-DIM B PER-CENT 1313400400019 14.74 0.05 0.32 1.132 2.378 0.74 1313400400020 ENDDATA 3 0 1313400400021 ENDSUBENT 20 0 1313400499999 SUBENT 13134005 20170724 14321313400500001 BIB 4 9 1313400500002 REACTION 1((92-U-234(N,F),,SIG)/(92-U-235(N,F),,SIG)) 1313400500003 2(92-U-234(N,F),,SIG) 1313400500004 DECAY-DATA (92-U-234,2.457E+5YR,A) 1313400500005 ERR-ANALYS (ERR-T) Total uncertainty 1313400500006 (ERR-1) Neutron energy 1313400500007 (ERR-2) Thickness correction 1313400500008 (ERR-3) Extrapolation correction 1313400500009 (ERR-6) Prompt neutron scattering 1313400500010 HISTORY (20170724A) On. ERR-ANALYS updated. 1313400500011 ENDBIB 9 0 1313400500012 COMMON 4 3 1313400500013 ERR-1 ERR-2 ERR-3 ERR-6 1313400500014 PER-CENT PER-CENT PER-CENT PER-CENT 1313400500015 0.75 0.30 0.30 0.20 1313400500016 ENDCOMMON 3 0 1313400500017 DATA 6 1 1313400500018 EN EN-ERR EN-RSL-FW DATA 1DATA 2ERR-T 1313400500019 MEV MEV MEV NO-DIM B PER-CENT 1313400500020 14.74 0.05 0.32 0.998 2.097 1.03 1313400500021 ENDDATA 3 0 1313400500022 ENDSUBENT 21 0 1313400599999 SUBENT 13134006 20170724 14321313400600001 BIB 4 9 1313400600002 REACTION 1((92-U-236(N,F),,SIG)/(92-U-235(N,F),,SIG)) 1313400600003 2(92-U-236(N,F),,SIG) 1313400600004 DECAY-DATA (92-U-236,2.343E+7YR,A) 1313400600005 ERR-ANALYS (ERR-T) Total uncertainty 1313400600006 (ERR-1) Neutron energy 1313400600007 (ERR-2) Thickness correction 1313400600008 (ERR-3) Extrapolation correction 1313400600009 (ERR-6) Prompt neutron scattering 1313400600010 HISTORY (20170724A) On. ERR-ANALYS updated. 1313400600011 ENDBIB 9 0 1313400600012 COMMON 4 3 1313400600013 ERR-1 ERR-2 ERR-3 ERR-6 1313400600014 PER-CENT PER-CENT PER-CENT PER-CENT 1313400600015 0.72 0.30 0.30 0.39 1313400600016 ENDCOMMON 3 0 1313400600017 DATA 6 1 1313400600018 EN EN-ERR EN-RSL-FW DATA 1DATA 2ERR-T 1313400600019 MEV MEV MEV NO-DIM B PER-CENT 1313400600020 14.74 0.05 0.32 0.791 1.661 1.07 1313400600021 ENDDATA 3 0 1313400600022 ENDSUBENT 21 0 1313400699999 SUBENT 13134007 20170724 14321313400700001 BIB 4 8 1313400700002 REACTION 1((92-U-238(N,F),,SIG)/(92-U-235(N,F),,SIG)) 1313400700003 2(92-U-238(N,F),,SIG) 1313400700004 DECAY-DATA (92-U-238,4.468E+9YR,A) 1313400700005 ERR-ANALYS (ERR-T) Total uncertainty 1313400700006 (ERR-1) Neutron energy 1313400700007 (ERR-2) Thickness correction 1313400700008 (ERR-3) Extrapolation correction 1313400700009 HISTORY (20170724A) On. ERR-ANALYS updated. 1313400700010 ENDBIB 8 0 1313400700011 COMMON 3 3 1313400700012 ERR-1 ERR-2 ERR-3 1313400700013 PER-CENT PER-CENT PER-CENT 1313400700014 0.66 0.30 0.30 1313400700015 ENDCOMMON 3 0 1313400700016 DATA 6 1 1313400700017 EN EN-ERR EN-RSL-FW DATA 1DATA 2ERR-T 1313400700018 MEV MEV MEV NO-DIM B PER-CENT 1313400700019 14.74 0.05 0.32 0.587 1.232 1.11 1313400700020 ENDDATA 3 0 1313400700021 ENDSUBENT 20 0 1313400799999 SUBENT 13134008 20170724 14321313400800001 BIB 4 10 1313400800002 REACTION 1((93-NP-237(N,F),,SIG)/(92-U-235(N,F),,SIG)) 1313400800003 2(93-NP-237(N,F),,SIG) 1313400800004 DECAY-DATA (93-NP-237,2.14E+6YR,A) 1313400800005 ERR-ANALYS (ERR-T) Total uncertainty 1313400800006 (ERR-1) Neutron energy 1313400800007 (ERR-2) Thickness correction 1313400800008 (ERR-3) Extrapolation correction 1313400800009 (ERR-5) Alpha-decay half-life of reaction sample 1313400800010 (ERR-6) Prompt neutron scattering 1313400800011 HISTORY (20170724A) On. ERR-ANALYS updated. 1313400800012 ENDBIB 10 0 1313400800013 COMMON 5 3 1313400800014 ERR-1 ERR-2 ERR-3 ERR-5 ERR-6 1313400800015 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 1313400800016 0.60 0.30 0.30 0.47 0.20 1313400800017 ENDCOMMON 3 0 1313400800018 DATA 6 1 1313400800019 EN EN-ERR EN-RSL-FW DATA 1DATA 2ERR-T 1313400800020 MEV MEV MEV NO-DIM B PER-CENT 1313400800021 14.74 0.05 0.32 1.060 2.227 1.42 1313400800022 ENDDATA 3 0 1313400800023 ENDSUBENT 22 0 1313400899999 SUBENT 13134009 20170724 14321313400900001 BIB 4 8 1313400900002 REACTION 1((94-PU-239(N,F),,SIG)/(92-U-235(N,F),,SIG)) 1313400900003 2(94-PU-239(N,F),,SIG) 1313400900004 DECAY-DATA (94-PU-239,2.411E+4YR,A) 1313400900005 ERR-ANALYS (ERR-T) Total uncertainty 1313400900006 (ERR-1) Neutron energy 1313400900007 (ERR-3) Extrapolation correction 1313400900008 (ERR-6) Prompt neutron scattering 1313400900009 HISTORY (20170724A) On. ERR-ANALYS updated. 1313400900010 ENDBIB 8 0 1313400900011 COMMON 3 3 1313400900012 ERR-1 ERR-3 ERR-6 1313400900013 PER-CENT PER-CENT PER-CENT 1313400900014 0.28 0.30 0.20 1313400900015 ENDCOMMON 3 0 1313400900016 DATA 6 1 1313400900017 EN EN-ERR EN-RSL-FW DATA 1DATA 2ERR-T 1313400900018 MEV MEV MEV NO-DIM B PER-CENT 1313400900019 14.74 0.05 0.32 1.152 2.420 1.14 1313400900020 ENDDATA 3 0 1313400900021 ENDSUBENT 20 0 1313400999999 SUBENT 13134010 20170724 14321313401000001 BIB 4 9 1313401000002 REACTION 1((94-PU-242(N,F),,SIG)/(92-U-235(N,F),,SIG)) 1313401000003 2(94-PU-242(N,F),,SIG) 1313401000004 DECAY-DATA (94-PU-242,3.735E+5YR,A) 1313401000005 ERR-ANALYS (ERR-T) Total uncertainty 1313401000006 (ERR-1) Neutron energy 1313401000007 (ERR-2) Thickness correction 1313401000008 (ERR-3) Extrapolation correction 1313401000009 (ERR-6) Prompt neutron scattering 1313401000010 HISTORY (20170724A) On. ERR-ANALYS updated. 1313401000011 ENDBIB 9 0 1313401000012 COMMON 4 3 1313401000013 ERR-1 ERR-2 ERR-3 ERR-6 1313401000014 PER-CENT PER-CENT PER-CENT PER-CENT 1313401000015 0.10 0.30 0.30 0.20 1313401000016 ENDCOMMON 3 0 1313401000017 DATA 6 1 1313401000018 EN EN-ERR EN-RSL-FW DATA 1DATA 2ERR-T 1313401000019 MEV MEV MEV NO-DIM B PER-CENT 1313401000020 14.74 0.05 0.32 0.967 2.032 1.04 1313401000021 ENDDATA 3 0 1313401000022 ENDSUBENT 21 0 1313401099999 ENDENTRY 10 0 1313499999999