ENTRY 22282 20130924 22362228200000001 SUBENT 22282001 20130924 22362228200100001 BIB 13 53 2228200100002 TITLE Measurements of neutron induced fission cross section 2228200100003 ratios of 232Th, 233U, 234U, 236U, 238U, 237Np, 242Pu 2228200100004 and 243Am relative to 235U around 14 MeV 2228200100005 AUTHOR (F.Manabe, K.Kanda, T.Iwasaki, H.Terayama, Y.Karino, 2228200100006 M.Baba, N.Hirakawa) 2228200100007 INSTITUTE (2JPNTOH) Department of Nuclear Engineering 2228200100008 REFERENCE (J,TRTU,52,(2),97,1988) 2228200100009 FACILITY (DYNAM,2JPNTOH) 4.5 MV Dynamitron accelerator facility 2228200100010 INC-SOURCE (D-T) Bombarding a tritium-titanium target by 750 keV 2228200100011 deuteron ions. 2228200100012 The target was deposited on a copper plate of 0.25 mm 2228200100013 (2.5 mg/cm2) thick, 16 mm diameter. 2228200100014 The neutrons of 14.9, 14.5, 14.0 and 13.5 MeV were 2228200100015 obtained at the emission angles of 0, 65, 100 and 2228200100016 150 deg with respect to the deuteron beam. 2228200100017 DETECTOR (FISCH) Back-to-back parallel plate ionization chamber.2228200100018 The counter gas was 90% Ar and 10% C-H4 mixture. 2228200100019 SAMPLE The samples were prepared by the electrodeposition on 2228200100020 the platinum plates, which were 36 mm in diam. and 2228200100021 0.3 or 0.4 mm in thickness, and sintered into the 2228200100022 oxide to fix them on the plates. 2228200100023 The diameter of the deposits was 25 mm. 2228200100024 The isotopic compositions of the samples were 2228200100025 determined by means of the alpha spectroscopy with a 2228200100026 high resolution surface barrier detector (except for 2228200100027 the 237Np measurements). 2228200100028 The 235U sample and another one were mounted back to 2228200100029 back on the midplane of the fission chamber. 2228200100030 (92-U-235,ENR=0.9991) Areal density 96.22 ug/cm 2228200100031 MONITOR 2(92-U-235(N,F),,SIG) 2228200100032 MONIT-REF 2(,M.R.Bhat,3,ENDF/B-V,1395,1979) 2228200100033 CORRECTION Corrected for 2228200100034 - room-returned neutrons, 2228200100035 - spontaneous fission, 2228200100036 - extrapolation from the tail of the fission spectrum 2228200100037 to the zero pulse height, 2228200100038 - anisotropy of the fission fragments, 2228200100039 - self-absorption of fission fragments in samples, 2228200100040 - impurities in the samples, 2228200100041 - chamber- and the target-scattered neutrons, 2228200100042 - parasitic neutrons, 2228200100043 - attenuation of neutron flux by backing plates, 2228200100044 - difference in solid angle subtended by samples to 2228200100045 target between the 235U sample and another one 2228200100046 Corrections for 235U: 2228200100047 - room-returned neutrons 1.5 - 4.7% 2228200100048 - extrapolation 0.2 - 1.5% 2228200100049 - self-absorption 2.4 - 2.5% 2228200100050 - sample impurity 0.1% 2228200100051 ERR-ANALYS (ERR-1) Number of 235U atoms (1.47%) 2228200100052 2(MONIT-ERR) 235U(n,f) monitor cross section (4%) 2228200100053 HISTORY (20080204C) SM 2228200100054 (20130924D) On. 22282.010-017 merged to 002-009 2228200100055 ENDBIB 53 0 2228200100056 COMMON 2 3 2228200100057 ERR-1 MONIT-ERR 2 2228200100058 PER-CENT PER-CENT 2228200100059 1.47 4. 2228200100060 ENDCOMMON 3 0 2228200100061 ENDSUBENT 60 0 2228200199999 SUBENT 22282002 20130924 22362228200200001 BIB 7 27 2228200200002 REACTION 1((90-TH-232(N,F),,SIG)/(92-U-235(N,F),,SIG)) 2228200200003 2(90-TH-232(N,F),,SIG) 2228200200004 SAMPLE Areal density 171.3 ug/cm2 2228200200005 CORRECTION Corrected for 2228200200006 - room-returned neutrons < O.l% 2228200200007 - extrapolation 0.5 - 1.8% 2228200200008 - self-absorption 2.9 - 3.0% 2228200200009 - chamber-scattered neutrons 0.6 - 0.7% 2228200200010 - target-scattered neutrons 0.5 - 0,7% 2228200200011 ERR-ANALYS (ERR-T,,,P) Total uncertainty 2228200200012 (ERR-2) Number of 232Th atoms (1.64%) 2228200200013 (ERR-3,0.802,0.887) Fission rate ratio (0.802-0.887%) 2228200200014 (ERR-4,0.197,0.276) Correction factor (0.197-0.276%) 2228200200015 COVARIANCE (XY,4,EN,MEV) 2228200200016 13.47 14.00 14.46 14.89 2228200200017 1 (Z,10,COR:ERR-T,PER-CENT) Macro-corr. coefficients 2228200200018 100 2228200200019 87 100 2228200200020 86 87 100 2228200200021 87 87 87 100 2228200200022 2 (Z,10,COR:ERR-T,PER-CENT) Macro-corr. coefficients 2228200200023 100 2228200200024 97 100 2228200200025 96 97 100 2228200200026 97 97 97 100 2228200200027 STATUS (TABLE) Tables IV-1 and IV-2 2228200200028 HISTORY (20130924A) On. Multiple reaction formalism introduced 2228200200029 ENDBIB 27 0 2228200200030 COMMON 1 3 2228200200031 ERR-2 2228200200032 PER-CENT 2228200200033 1.64 2228200200034 ENDCOMMON 3 0 2228200200035 DATA 6 4 2228200200036 EN EN-ERR DATA 1ERR-T 1DATA 2ERR-T 22228200200037 MEV MEV NO-DIM PER-CENT B PER-CENT 2228200200038 13.47 0.18 0.150 2.41 0.300 4.67 2228200200039 14.00 0.06 0.158 2.38 0.327 4.65 2228200200040 14.46 0.16 0.166 2.37 0.348 4.65 2228200200041 14.89 0.29 0.181 2.38 0.380 4.65 2228200200042 ENDDATA 6 0 2228200200043 ENDSUBENT 42 0 2228200299999 SUBENT 22282003 20130924 22362228200300001 BIB 7 28 2228200300002 REACTION 1((92-U-233(N,F),,SIG)/(92-U-235(N,F),,SIG)) 2228200300003 2(92-U-233(N,F),,SIG) 2228200300004 SAMPLE (92-U-233,ENR=0.9947) Areal density 129.9 ug/cm2 2228200300005 CORRECTION Corrected for 2228200300006 - room-returned neutrons 2.1 - 3.9% 2228200300007 - extrapolation 1.9 - 3.7% 2228200300008 - self-absorption 2.7% 2228200300009 - sample impurity 0.3% 2228200300010 - chamber-scattered neutrons 0.3% 2228200300011 - target-scattered neutrons 0,3% 2228200300012 ERR-ANALYS (ERR-T,,,P) Total uncertainty 2228200300013 (ERR-2) Number of 233U atoms (0.487%) 2228200300014 (ERR-3,1.30,1.51) Fission rate ratio (1.30-1.51%) 2228200300015 (ERR-4,0.109,0.131) Correction factor (0.109-0.131%) 2228200300016 COVARIANCE (XY,4,EN,MEV) 2228200300017 13.47 14.00 14.46 14.89 2228200300018 1 (Z,10,COR:ERR-T,PER-CENT) Macro-corr. coefficients 2228200300019 100 2228200300020 81 100 2228200300021 79 81 100 2228200300022 78 80 79 100 2228200300023 2 (Z,10,COR:ERR-T,PER-CENT) Macro-corr. coefficients 2228200300024 100 2228200300025 96 100 2228200300026 95 96 100 2228200300027 95 96 95 100 2228200300028 STATUS (TABLE) Tables V-1 and V-2 2228200300029 HISTORY (20130924A) On. Multiple reaction formalism introduced 2228200300030 ENDBIB 28 0 2228200300031 COMMON 1 3 2228200300032 ERR-2 2228200300033 PER-CENT 2228200300034 0.487 2228200300035 ENDCOMMON 3 0 2228200300036 DATA 6 4 2228200300037 EN EN-ERR DATA 1ERR-T 1DATA 2ERR-T 22228200300038 MEV MEV NO-DIM PER-CENT B PER-CENT 2228200300039 13.47 0.18 1.18 2.19 2.35 4.56 2228200300040 14.00 0.06 1.19 2.17 2.46 4.55 2228200300041 14.46 0.16 1.15 2.13 2.41 4.53 2228200300042 14.89 0.29 1.14 2.04 2.39 4.49 2228200300043 ENDDATA 6 0 2228200300044 ENDSUBENT 43 0 2228200399999 SUBENT 22282004 20130924 22362228200400001 BIB 7 28 2228200400002 REACTION 1((92-U-234(N,F),,SIG)/(92-U-235(N,F),,SIG)) 2228200400003 2(92-U-234(N,F),,SIG) 2228200400004 SAMPLE (92-U-234,ENR=0.9908) Areal density 136.0 ug/cm2 2228200400005 CORRECTION Corrected for 2228200400006 - room-returned neutrons < 0.1% 2228200400007 - extrapolation 1.4 - 3.1% 2228200400008 - self-absorption 2.7 - 2.8% 2228200400009 - sample impurity 0.5 - 0.6% 2228200400010 - chamber-scattered neutrons 0.0% 2228200400011 - target-scattered neutrons 0.1 - 0.2% 2228200400012 ERR-ANALYS (ERR-T,,,P) Total uncertainty 2228200400013 (ERR-2) Number of 234U atoms (0.597%) 2228200400014 (ERR-3,1.13,1.41) Fission rate ratio (1.13-1.41%) 2228200400015 (ERR-4,0.114,0.160) Correction factor (0.114-0.160%) 2228200400016 COVARIANCE (XY,4,EN,MEV) 2228200400017 13.47 14.00 14.46 14.89 2228200400018 1 (Z,10,COR:ERR-T,PER-CENT) Macro-corr. coefficients 2228200400019 100 2228200400020 76 100 2228200400021 78 77 100 2228200400022 75 76 77 100 2228200400023 2 (Z,10,COR:ERR-T,PER-CENT) Macro-corr. coefficients 2228200400024 100 2228200400025 95 100 2228200400026 95 95 100 2228200400027 95 95 95 100 2228200400028 STATUS (TABLE) Tables VI-1 and IV-2 2228200400029 HISTORY (20130924A) On. Multiple reaction formalism introduced 2228200400030 ENDBIB 28 0 2228200400031 COMMON 1 3 2228200400032 ERR-2 2228200400033 PER-CENT 2228200400034 0.597 2228200400035 ENDCOMMON 3 0 2228200400036 DATA 6 4 2228200400037 EN EN-ERR DATA 1ERR-T 1DATA 2ERR-T 22228200400038 MEV MEV NO-DIM PER-CENT B PER-CENT 2228200400039 13.47 0.18 1.00 2.15 2.00 4.54 2228200400040 14.00 0.06 0.983 1.99 2.03 4.47 2228200400041 14.46 0.16 0.999 2.03 2.09 4.48 2228200400042 14.89 0.29 1.01 1.96 2.13 4.46 2228200400043 ENDDATA 6 0 2228200400044 ENDSUBENT 43 0 2228200499999 SUBENT 22282005 20130924 22362228200500001 BIB 7 28 2228200500002 REACTION 1((92-U-236(N,F),,SIG)/(92-U-235(N,F),,SIG)) 2228200500003 2(92-U-236(N,F),,SIG) 2228200500004 SAMPLE (92-U-236,ENR=0.8913) Areal density of 101.5 ug/cm2 2228200500005 CORRECTION Corrected for 2228200500006 - room-returned neutrons 0.3 - 0.6% 2228200500007 - extrapolation 0.2 - 0.8% 2228200500008 - self-absorption 2.5 - 2.6% 2228200500009 - sample impurity 12.6 -13.3% 2228200500010 - chamber-scattered neutrons 0.3 - 0.4% 2228200500011 - target-scattered neutrons 0.3 - 0.5% 2228200500012 ERR-ANALYS (ERR-T,,,P) Total uncertainty 2228200500013 (ERR-2) Number of 236U atoms (1.68%) 2228200500014 (ERR-3,0.941,0.965) Fission rate ratio (0.941-0.965%) 2228200500015 (ERR-4,0.838,0.897) Correction factor (0.838-0.897%) 2228200500016 COVARIANCE (XY,4,EN,MEV) 2228200500017 13.47 14.00 14.46 14.89 2228200500018 1 (Z,10,COR:ERR-T,PER-CENT) Macro-corr. coefficients 2228200500019 100 2228200500020 74 100 2228200500021 73 74 100 2228200500022 73 74 74 100 2228200500023 2 (Z,10,COR:ERR-T,PER-CENT) Macro-corr. coefficients 2228200500024 100 2228200500025 93 100 2228200500026 93 93 100 2228200500027 93 93 93 100 2228200500028 STATUS (TABLE) Tables VII-1 and VII-2 2228200500029 HISTORY (20130924A) On. Multiple reaction formalism introduced 2228200500030 ENDBIB 28 0 2228200500031 COMMON 1 3 2228200500032 ERR-2 2228200500033 PER-CENT 2228200500034 1.68 2228200500035 ENDCOMMON 3 0 2228200500036 DATA 6 4 2228200500037 EN EN-ERR DATA 1ERR-T 1DATA 2ERR-T 22228200500038 MEV MEV NO-DIM PER-CENT B PER-CENT 2228200500039 13.47 0.18 0.757 2.36 1.51 4.64 2228200500040 14.00 0.06 0.786 2.33 1.63 4.63 2228200500041 14.46 0.16 0.797 2.34 1.70 4.64 2228200500042 14.89 0.29 0.803 2.34 1.69 4.63 2228200500043 ENDDATA 6 0 2228200500044 ENDSUBENT 43 0 2228200599999 SUBENT 22282006 20130924 22362228200600001 BIB 7 28 2228200600002 REACTION 1((92-U-238(N,F),,SIG)/(92-U-235(N,F),,SIG)) 2228200600003 2(92-U-238(N,F),,SIG) 2228200600004 SAMPLE (92-U-238,ENR=0.9996) Areal density of 108.0 ug/cm2 2228200600005 CORRECTION Corrected for 2228200600006 - room-returned neutrons < 0.1% 2228200600007 - extrapolation 0.2 - 0.9% 2228200600008 - self-absorption 2.5 - 2.6% 2228200600009 - sample impurity 0.1% 2228200600010 - chamber-scattered neutrons 0.5 - 0.7% 2228200600011 - target-scattered neutrons 0.4 - 0.7% 2228200600012 ERR-ANALYS (ERR-T,,,P) Total uncertainty 2228200600013 (ERR-2) Number of 238U atoms (1.57%) 2228200600014 (ERR-3,0.890,0.912) Fission rate ratio (0.890-0.912%) 2228200600015 (ERR-4,0.187,0.271) Correction factor (0.187-0.271%) 2228200600016 COVARIANCE (XY,4,EN,MEV) 2228200600017 13.47 14.00 14.46 14.89 2228200600018 1 (Z,10,COR:ERR-T,PER-CENT) Macro-corr. coefficients 2228200600019 100 2228200600020 78 100 2228200600021 78 78 100 2228200600022 78 78 78 100 2228200600023 2 (Z,10,COR:ERR-T,PER-CENT) Macro-corr. coefficients 2228200600024 100 2228200600025 96 100 2228200600026 96 96 100 2228200600027 96 96 96 100 2228200600028 STATUS (TABLE) Tables VIII-1 and VIII-2 2228200600029 HISTORY (20130924A) On. Multiple reaction formalism introduced 2228200600030 ENDBIB 28 0 2228200600031 COMMON 1 3 2228200600032 ERR-2 2228200600033 PER-CENT 2228200600034 1.57 2228200600035 ENDCOMMON 3 0 2228200600036 DATA 6 4 2228200600037 EN EN-ERR DATA 1ERR-T 1DATA 2ERR-T 22228200600038 MEV MEV NO-DIM PER-CENT B PER-CENT 2228200600039 13.47 0.18 0.544 2.02 1.08 4.48 2228200600040 14.00 0.06 0.560 2.00 1.16 4.47 2228200600041 14.46 0.16 0.572 2.01 1.20 4.48 2228200600042 14.89 0.29 0.584 2.01 1.23 4.47 2228200600043 ENDDATA 6 0 2228200600044 ENDSUBENT 43 0 2228200699999 SUBENT 22282007 20130924 22362228200700001 BIB 7 28 2228200700002 REACTION 1((93-NP-237(N,F),,SIG)/(92-U-235(N,F),,SIG)) 2228200700003 2(93-NP-237(N,F),,SIG) 2228200700004 SAMPLE (93-NP-237,ENR=1.000) Areal density 90.88 ug/cm2 2228200700005 CORRECTION Corrected for 2228200700006 - room-returned neutrons < 0.1% 2228200700007 - extrapolation 0.3 - 1.1% 2228200700008 - self-absorption 2.4 - 2.5% 2228200700009 - sample impurity 0.0% 2228200700010 - chamber-scattered neutrons 0.0% 2228200700011 - target-scattered neutrons 0.1 - 0.2% 2228200700012 ERR-ANALYS (ERR-T,,,P) Total uncertainty 2228200700013 (ERR-2) Number of 237Np atoms (0.661%) 2228200700014 (ERR-3,0.977,1.04) Fission rate ratio (0.977-1.04%) 2228200700015 (ERR-4,0.116,0.168) Correction factor (0.116-0.168%) 2228200700016 COVARIANCE (XY,4,EN,MEV) 2228200700017 13.47 14.00 14.46 14.89 2228200700018 1 (Z,10,COR:ERR-T,PER-CENT) Macro-corr. coefficients 2228200700019 100 2228200700020 70 100 2228200700021 71 72 100 2228200700022 70 72 72 100 2228200700023 2 (Z,10,COR:ERR-T,PER-CENT) Macro-corr. coefficients 2228200700024 100 2228200700025 94 100 2228200700026 94 95 100 2228200700027 94 95 95 100 2228200700028 STATUS (TABLE) Tables IX-1 and IX-2 2228200700029 HISTORY (20130924A) On. Multiple reaction formalism introduced 2228200700030 ENDBIB 28 0 2228200700031 COMMON 1 3 2228200700032 ERR-2 2228200700033 PER-CENT 2228200700034 0.661 2228200700035 ENDCOMMON 3 0 2228200700036 DATA 6 4 2228200700037 EN EN-ERR DATA 1ERR-T 1DATA 2ERR-T 22228200700038 MEV MEV NO-DIM PER-CENT B PER-CENT 2228200700039 13.47 0.18 1.11 1.94 2.21 4.45 2228200700040 14.00 0.06 1.06 1.91 2.18 4.43 2228200700041 14.46 0.16 1.08 1.90 2.25 4.43 2228200700042 14.89 0.29 1.07 1.90 2.26 4.43 2228200700043 ENDDATA 6 0 2228200700044 ENDSUBENT 43 0 2228200799999 SUBENT 22282008 20130924 22362228200800001 BIB 7 27 2228200800002 REACTION 1((94-PU-242(N,F),,SIG)/(92-U-235(N,F),,SIG)) 2228200800003 2(94-PU-242(N,F),,SIG) 2228200800004 SAMPLE (94-PU-242,ENR=0.9984) Areal density 10.46 ug/cm2 2228200800005 CORRECTION Corrected for 2228200800006 - room-returned neutrons < 0.1% 2228200800007 - spontaneous fission 2.4 - 2.6% 2228200800008 - extrapolation 0.1 - 0.6% 2228200800009 - self-absorption 1.9% 2228200800010 - sample impurity 0.2% 2228200800011 - chamber-scattered neutrons < 0.1% 2228200800012 - target-scattered neutrons 0.1 - 0.2% 2228200800013 ERR-ANALYS (ERR-T,,,P) Total uncertainty 2228200800014 (ERR-2) Number of 242Pu atoms (0.816%) 2228200800015 (ERR-3,0.773,0.825) Fission rate ratio (0.773-0.825%) 2228200800016 (ERR-4,0.131,0.151) Correction factor (0.131-0.151%) 2228200800017 COVARIANCE (XY,4,EN,MEV) 2228200800018 14.00 14.46 14.89 2228200800019 1 (Z,10,COR:ERR-T,PER-CENT) Macro-corr. coefficients 2228200800020 100 2228200800021 83 100 2228200800022 84 84 100 2228200800023 2 (Z,10,COR:ERR-T,PER-CENT) Macro-corr. coefficients 2228200800024 100 2228200800025 97 100 2228200800026 97 97 100 2228200800027 STATUS (TABLE) Tables X-1 and X-2 2228200800028 HISTORY (20130924A) On. Multiple reaction formalism introduced 2228200800029 ENDBIB 27 0 2228200800030 COMMON 1 3 2228200800031 ERR-2 2228200800032 PER-CENT 2228200800033 0.816 2228200800034 ENDCOMMON 3 0 2228200800035 DATA 6 3 2228200800036 EN EN-ERR DATA 1ERR-T 1DATA 2ERR-T 22228200800037 MEV MEV NO-DIM PER-CENT B PER-CENT 2228200800038 14.00 0.06 0.998 1.86 2.06 4.41 2228200800039 14.46 0.16 1.00 1.89 2.10 4.42 2228200800040 14.89 0.29 0.989 1.87 2.08 4.41 2228200800041 ENDDATA 5 0 2228200800042 ENDSUBENT 41 0 2228200899999 SUBENT 22282009 20130924 22362228200900001 BIB 7 27 2228200900002 REACTION 1((95-AM-243(N,F),,SIG)/(92-U-235(N,F),,SIG)) 2228200900003 2(95-AM-243(N,F),,SIG) 2228200900004 SAMPLE (95-AM-243,ENR=0.9959) Areal density 20.33 ug/cm2 2228200900005 CORRECTION Corrected for 2228200900006 - room-returned neutrons < 0.1% 2228200900007 - spontaneous fission 38.9 -43.7% 2228200900008 - extrapolation 1.0 - 2.4% 2228200900009 - self-absorption 1.9 - 2.0% 2228200900010 - sample impurity 0.5% 2228200900011 - chamber-scattered neutrons < 0.1% 2228200900012 - target-scattered neutrons < 0.2% 2228200900013 ERR-ANALYS (ERR-T,,,P) Total uncertainty 2228200900014 (ERR-2) Number of 243Am atoms (2.08%) 2228200900015 (ERR-3,0.909,0.945) Fission rate ratio (0.909-0.945%) 2228200900016 (ERR-4,0.135,0.170) Correction factor (0.135-0.170%) 2228200900017 COVARIANCE (XY,4,EN,MEV) 2228200900018 14.00 14.46 14.89 2228200900019 1 (Z,10,COR:ERR-T,PER-CENT) Macro-corr. coefficients 2228200900020 100 2228200900021 89 100 2228200900022 89 89 100 2228200900023 2 (Z,10,COR:ERR-T,PER-CENT) Macro-corr. coefficients 2228200900024 100 2228200900025 97 100 2228200900026 97 97 100 2228200900027 STATUS (TABLE) Tables XI-1 and XI-2 2228200900028 HISTORY (20130924A) On. Multiple reaction formalism introduced 2228200900029 ENDBIB 27 0 2228200900030 COMMON 1 3 2228200900031 ERR-2 2228200900032 PER-CENT 2228200900033 2.08 2228200900034 ENDCOMMON 3 0 2228200900035 DATA 6 3 2228200900036 EN EN-ERR DATA 1ERR-T 1DATA 2ERR-T 22228200900037 MEV MEV NO-DIM PER-CENT B PER-CENT 2228200900038 14.00 0.06 1.08 2.47 2.23 4.70 2228200900039 14.46 0.16 1.05 2.46 2.21 4.70 2228200900040 14.89 0.29 1.06 2.46 2.22 4.69 2228200900041 ENDDATA 5 0 2228200900042 ENDSUBENT 41 0 2228200999999 NOSUBENT 22282010 20130924 22362228201000001 NOSUBENT 22282011 20130924 22362228201100001 NOSUBENT 22282012 20130924 22362228201200001 NOSUBENT 22282013 20130924 22362228201300001 NOSUBENT 22282014 20130924 22362228201400001 NOSUBENT 22282015 20130924 22362228201500001 NOSUBENT 22282016 20130924 22362228201600001 NOSUBENT 22282017 20130924 22362228201700001 ENDENTRY 17 0 2228299999999