ENTRY 23281 20230324 2328100000001 SUBENT 23281001 20230324 20231011 2328100100001 BIB 13 62 2328100100002 TITLE Neutron-induced fission cross section of 240Pu from 2328100100003 0.5 MeV to 3 MeV 2328100100004 AUTHOR (P.Salvador-Castineira, T.Brys, R.Eykens, F.-J.Hambsch,2328100100005 A.Gook, A.Moens, S.Oberstedt, G.Sibbens, D.Vanleeuw, 2328100100006 M.Vidali, C.Pretel) 2328100100007 INSTITUTE (2ZZZGEL,2SPNUPC) 2328100100008 REFERENCE (J,PR/C,92,014620,2015) 2328100100009 (T,SALVADOR-CASTINEIRA,201409) 2328100100010 Thesis submitted to Univ. Politec. de Catalunya 2328100100011 (J,PPRC,64,177,2015) 2328100100012 238U,237Np,240Pu,242Pu(n,f) cross sections in fig 2328100100013 (J,NDS,119,55,2014) 2328100100014 240Pu,242Pu(n,f) cross sections in fig 2328100100015 (J,PPRC,47,150,2013) Prelim.publication on figures. 2328100100016 REL-REF (O,,P.Salvador-Castineira+,J,PR/C,92,044606,2015) 2328100100017 242Pu(n,f) cross section compiled separately 2328100100018 FACILITY (VDG,2ZZZGEL) 2328100100019 INC-SPECT 7Li(p,n0)7Be and 7Li(p,n1)7Be neutrons 2328100100020 DETECTOR (FISCH) Twin Frisch-grid ionization chamber (TFGIC) 2328100100021 for fission fragments detection. 2328100100022 The sample under study and reference sample were 2328100100023 placed in a back-to-back geometry. 2328100100024 SAMPLE 240Pu: Prepared by electrodeposition on Al backing. 2328100100025 mass of 240Pu = 93 ug (0.4%) 2328100100026 diameter = 30 mm (0.1%) 2328100100027 areal density = 13.19 ug/cm2 (0.4%) 2328100100028 alpha activity= 0.780 MBq (0.4%) 2328100100029 (94-PU-240,ENR=0.998915) 2328100100030 (94-PU-238,ENR=0.000733) 2328100100031 (94-PU-239,ENR=0.000144) 2328100100032 (94-PU-241,ENR=0.000041) 2328100100033 (94-PU-242,ENR=0.000203) 2328100100034 (94-PU-244,ENR=0.000001) 2328100100035 COMMENT Paula Salvador-Castineira (2020-11-30): 2328100100036 The 240Pu(n,f) cross sections measured relative to 2328100100037 (1) 237Np(n,f) and 235U(n,f) normalized with their 2328100100038 ENDF cross sections, and 2328100100039 (2) 238U(n,f) normalized with the experimental 2328100100040 238U(n,f) cross section (determined relative to 2328100100041 the 235U(n,f) ENDF cross section) 2328100100042 are adopted as the final data sets. 2328100100043 CORRECTION Corrected for 2328100100044 - Electronic threshold 2328100100045 - Spontaneous fission half-life 2328100100046 - Self-absorption and efficiency 2328100100047 - Neutron spectrum, sample inhomogeneity, solid angle 2328100100048 - 7Li(p,n1)7Be neutrons 2328100100049 - Background neutrons 2328100100050 ERR-ANALYS (ERR-T) Total uncertainty. 2328100100051 Statistical uncertainty is around 0.5% except for a 2328100100052 single case where it amounts to 1.4%. 2328100100053 (ERR-1,,1.1) 240Pu(sf) counts (<1.1%) 2328100100054 (ERR-2) 240Pu mass (0.4%) 2328100100055 (ERR-3) Efficiency - 240Pu (1%) 2328100100056 (ERR-4) Efficiency - monitor (1%) 2328100100057 (ERR-5) Sample purity (0.001%) 2328100100058 (ERR-6,,0.1) 240Pu neutron spectrum shape (<0.2%) 2328100100059 (ERR-7) Thermalized neutron flux - 240Pu (0.5%) 2328100100060 (ERR-8) Thermalized neutron flux - monitor (0.5%) 2328100100061 HISTORY (20151226C) M.M. 2328100100062 (20201201A) On. Entry recompiled. 2328100100063 (20230324U) SD: Ref. PPRC,47,150 added. 2328100100064 ENDBIB 62 0 2328100100065 COMMON 6 3 2328100100066 ERR-2 ERR-3 ERR-4 ERR-5 ERR-7 ERR-8 2328100100067 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2328100100068 0.4 1. 1. 0.001 0.5 0.5 2328100100069 ENDCOMMON 3 0 2328100100070 ENDSUBENT 69 0 2328100199999 SUBENT 23281002 20201201 22952328100200001 BIB 9 22 2328100200002 REACTION (94-PU-240(N,F),,SIG) 2328100200003 INC-SOURCE (P-LI7) 2328100200004 MONITOR (93-NP-237(N,F),,SIG) 2328100200005 MONIT-REF (,,3,ENDF/B-VII.1,,2011) 2328100200006 SAMPLE 237Np:Prepared by vacuum deposition on stainless steel.2328100200007 mass of 237Np = 390 ug (0.3%) 2328100200008 diameter = 12.7 mm 2328100200009 areal density = 308 ug/cm2 (0.3%) 2328100200010 alpha activity= 0.001 MBq (0.1%) 2328100200011 purity = 99.8% (with 0.2% 238Pu) 2328100200012 ERR-ANALYS (ERR-9) 237Np mass (0.3%) 2328100200013 (ERR-10,,0.2) 237Np neutron spectrum shape (<0.2%) 2328100200014 (ERR-11) 240Pu statistics (0.5%) 2328100200015 (ERR-12) 237Np statistics (0.5%) 2328100200016 (MONIT-ERR) 237Np(n,f) cross section (2.2-4%) 2328100200017 COMMENT By compiler (2020-10-12): 2328100200018 - The range of MONIT-ERR/MONIT is 2.7-5.3%. 2328100200019 - The systematic uncertainty associated with the 2328100200020 measurement originated from the reference cross 2328100200021 section is 2.2-4% in Table II of PRC92(2015)014620. 2328100200022 STATUS (TABLE) Table B.5 of thesis 2328100200023 HISTORY (20201201A) On. Data rounded. MONIT(-ERR) added. 2328100200024 ENDBIB 22 0 2328100200025 COMMON 3 3 2328100200026 ERR-9 ERR-11 ERR-12 2328100200027 PER-CENT PER-CENT PER-CENT 2328100200028 0.3 0.5 0.5 2328100200029 ENDCOMMON 3 0 2328100200030 DATA 6 10 2328100200031 EN EN-RSL-HW DATA ERR-T MONIT MONIT-ERR 2328100200032 MEV MEV B B B B 2328100200033 0.5 0.040 0.404 0.018 0.486 0.020 2328100200034 0.7 0.037 0.88 0.05 1.068 0.057 2328100200035 0.8 0.036 1.07 0.05 1.259 0.059 2328100200036 0.9 0.024 1.28 0.05 1.375 0.056 2328100200037 1.0 0.023 1.39 0.05 1.468 0.051 2328100200038 1.2 0.022 1.45 0.05 1.520 0.047 2328100200039 1.3 0.022 1.44 0.04 1.559 0.044 2328100200040 1.6 0.028 1.53 0.04 1.642 0.044 2328100200041 1.7 0.028 1.54 0.04 1.658 0.044 2328100200042 1.8 0.027 1.55 0.05 1.675 0.045 2328100200043 ENDDATA 12 0 2328100200044 ENDSUBENT 43 0 2328100299999 SUBENT 23281003 20201201 22952328100300001 BIB 9 22 2328100300002 REACTION (94-PU-240(N,F),,SIG) 2328100300003 INC-SOURCE (P-T) 2328100300004 MONITOR (92-U-235(N,F),,SIG) 2328100300005 Comment by compiler (2020-12-01): 2328100300006 The 235U(n,f) cross section is 1.284(7) b in Table B.32328100300007 while 1.193(7) b in Table B.10. It is 1.286722 b at 2328100300008 2.0 MeV in the ENDF/B-VII.1 source file. 2328100300009 MONIT-REF (,,3,ENDF/B-VII.1,,2011) 2328100300010 ANALYSIS [240Pu(n,f)/238U(n,f)]exp*[238U(n,f)/235U(n,f)]exp 2328100300011 multiplied by ENDF/B-VII.1 235U(n,f) cross section 2328100300012 SAMPLE 238U:Prepared by vacuum deposition. 2328100300013 mass of 238U = 577 ug (0.4%) 2328100300014 diameter = 30 mm 2328100300015 areal density = 81.7 ug/cm2 (0.4%) 2328100300016 alpha activity= 7 MBq (0.5%) 2328100300017 (92-U-238,ENR=0.9999) with 234U (<0.02%) 2328100300018 ERR-ANALYS (ERR-9,1.5,2.) 235U mass (1.5-2%) 2328100300019 (ERR-11) 240Pu statistics (0.5%) 2328100300020 (ERR-12) 235U statistics (0.5%) 2328100300021 (MONIT-ERR) 235U(n,f) cross section (<0.8%) 2328100300022 STATUS (TABLE) Tables B.3 and B.7 of thesis 2328100300023 HISTORY (20201201A) On. Data rounded. MONIT(-ERR) added. 2328100300024 ENDBIB 22 0 2328100300025 COMMON 2 3 2328100300026 ERR-11 ERR-12 2328100300027 PER-CENT PER-CENT 2328100300028 0.5 0.5 2328100300029 ENDCOMMON 3 0 2328100300030 DATA 6 12 2328100300031 EN EN-RSL-HW DATA ERR-T MONIT MONIT-ERR 2328100300032 MEV MEV B B B B 2328100300033 1.6 0.087 1.52 0.03 1.253 0.007 2328100300034 1.7 0.085 1.53 0.03 2328100300035 1.8 0.083 1.57 0.03 1.271 0.007 2328100300036 1.9 0.080 1.61 0.04 2328100300037 2.0 0.078 1.64 0.04 1.284 0.007 2328100300038 2.2 0.074 1.65 0.04 1.277 0.007 2328100300039 2.3 0.073 1.64 0.04 2328100300040 2.4 0.071 1.63 0.04 1.267 0.007 2328100300041 2.5 0.070 1.69 0.04 1.262 0.007 2328100300042 2.6 0.068 1.70 0.04 1.257 0.007 2328100300043 2.8 0.065 1.72 0.04 1.240 0.008 2328100300044 3.0 0.063 1.74 0.04 2328100300045 ENDDATA 14 0 2328100300046 ENDSUBENT 45 0 2328100399999 SUBENT 23281004 20201201 22952328100400001 BIB 9 20 2328100400002 REACTION (94-PU-240(N,F),,SIG) 2328100400003 INC-SOURCE (P-LI7) 2328100400004 MONITOR (92-U-235(N,F),,SIG) 2328100400005 MONIT-REF (,,3,ENDF/B-VII.1,,2011) 2328100400006 SAMPLE 235U:Prepared by vacuum deposition on stainless steel. 2328100400007 mass of 235U = 584 ug (2%) 2328100400008 diameter = 28 mm 2328100400009 areal density = 94.8 ug/cm2 (2%) 2328100400010 alpha activity= 265.7 Bq (2%) incl. 234U activity 2328100400011 (92-U-235,ENR=0.995) 2328100400012 (92-U-234,ENR=0.002) 2328100400013 (92-U-236,ENR=0.0003) 2328100400014 (92-U-238,ENR=0.003) 2328100400015 ERR-ANALYS (ERR-9,1.5,2.) 235U mass (1.5-2%) 2328100400016 (ERR-11) 240Pu statistics (0.5%) 2328100400017 (ERR-12) 235U statistics (0.5%) 2328100400018 (MONIT-ERR) 235U(n,f) cross section (<0.8%) 2328100400019 COMMENT By compiler (2020-10-12): 2328100400020 STATUS (TABLE) Table B.6 of thesis 2328100400021 HISTORY (20201201A) On. Data rounded. MONIT(-ERR) added. 2328100400022 ENDBIB 20 0 2328100400023 COMMON 2 3 2328100400024 ERR-11 ERR-12 2328100400025 PER-CENT PER-CENT 2328100400026 0.5 0.5 2328100400027 ENDCOMMON 3 0 2328100400028 DATA 6 5 2328100400029 EN EN-RSL-HW DATA ERR-T MONIT MONIT-ERR 2328100400030 MEV MEV B B B B 2328100400031 0.5 0.054 0.420 0.010 1.138 0.007 2328100400032 0.8 0.047 1.04 0.02 1.115 0.007 2328100400033 1.2 0.042 1.45 0.03 1.203 0.006 2328100400034 1.6 0.037 1.58 0.04 1.253 0.007 2328100400035 1.8 0.036 1.59 0.03 1.270 0.007 2328100400036 ENDDATA 7 0 2328100400037 ENDSUBENT 36 0 2328100499999 SUBENT 23281005 20201201 22952328100500001 BIB 4 8 2328100500002 REACTION (94-PU-240(N,F),,SIG,,AV) 2328100500003 ANALYSIS Weighted average of measured cross sections relative 2328100500004 to 237Np(n,f), 238U(n,f) and 235U(n,f) 2328100500005 STATUS (TABLE) Data received from F.-J.Hambsch 2328100500006 (DEP,23281002) Measurement relative to 237Np 2328100500007 (DEP,23281003) Measurement relative to 238U 2328100500008 (DEP,23281004) Measurement relative to 235U 2328100500009 HISTORY (20160401R) Data received from F.-J.Hambsch. 2328100500010 ENDBIB 8 0 2328100500011 NOCOMMON 0 0 2328100500012 DATA 4 19 2328100500013 EN EN-RSL-HW DATA ERR-T 2328100500014 MEV MEV B B 2328100500015 0.5 0.054 0.416 0.018 2328100500016 0.7 0.037 0.882 0.050 2328100500017 0.8 0.047 1.04 0.05 2328100500018 0.9 0.024 1.28 0.05 2328100500019 1.0 0.023 1.39 0.05 2328100500020 1.2 0.042 1.45 0.05 2328100500021 1.3 0.022 1.44 0.04 2328100500022 1.6 0.087 1.54 0.04 2328100500023 1.7 0.085 1.53 0.04 2328100500024 1.8 0.083 1.58 0.05 2328100500025 1.9 0.080 1.61 0.04 2328100500026 2.0 0.078 1.64 0.04 2328100500027 2.2 0.074 1.65 0.04 2328100500028 2.3 0.073 1.64 0.04 2328100500029 2.4 0.071 1.64 0.04 2328100500030 2.5 0.070 1.69 0.04 2328100500031 2.6 0.068 1.70 0.04 2328100500032 2.8 0.065 1.72 0.04 2328100500033 3.0 0.063 1.74 0.04 2328100500034 ENDDATA 21 0 2328100500035 ENDSUBENT 34 0 2328100599999 ENDENTRY 5 0 2328199999999