SUBENT 22282001 20080204 20080402 20080318 2192 BIB 13 77 TITLE .Measurements of Neutron Induced Fission Cross Sections Ratios of 232Th, 233U, 234U, 236U, 238U, 237Np, 242Pu and 243Am Relative to 235U around 14 MeV AUTHOR (Fumitoshi MANABE, Kazutaka KANDA, Tomohiko IWASAKI, Hirimichi TERAYAMA, Yoshiji KARINO, Mamoru BABA, Naohiro HIRAKAWA) INSTITUTE (2JPNTOH) Department of Nuclear Engineering REFERENCE (J,TRTU,52,(2),97,1988) THE TECHNOLOGY REPORTS OF THE TOHOKU UNIVERSITY SENDAI, JAPAN, Vol.52, No.2 Main reference, data tables are given FACILITY (DYNAM) Tohoku University 4.5 MV DYNAMITRON accelerator facility INC-SOURCE (D-T) Bombarding a tritium-titanium target by 750 keV deuteron ions. The target was deposited on a copper plate of 0.25 mm (2.5 milligram/cm2) thick, 16 mm diameter. INC-SPECT .The neutrons of 14.9, 14.5, 14.0 and 13.5 MeV were obtained, respectively, at the emission angles of 0, 65, 100 and 150 degrees with respect to the deuteron beam. METHOD (STTA) The 235U sample and another one were mounted back to back on the midplane of the fission chamber. DETECTOR (FISCH) The fission chamber used in this study was a back-to-back parallel plate ionization chamber. The counter gas was 90% Argon and 10% C-H4 mixture. (SI) Low geometry counter with a silicon detector - for the absolute number densities of atoms in the samples. (SIBAR) Surface-barrier silicon detector for alpha registration used for sample analysis SAMPLE .The samples were prepared by the electrodeposition on the platinum plates, which were 36 mm in diam. and 0.3 or 0.4 mm in thickness, and sintered into the oxide to fix them on the plates. The diameter of the deposits was 25 mm. The isotopic compositions of the samples were determined by means of the alpha spectroscopy with a high resolution surface barrier detector (except for the Np-237 measurements). .Monitor sample U-235 has arial density 96.22 microgram/cm2. Sample content ==> Element content,% number of atoms U-235 99.91 (10.64+-0.16)E17; U-234 0.029 0.003E+17; U-236 0.017 0.002E+17; U-238 0.041 0.004E+17 CORRECTION .Corrections were made for the following effects: 1. The room-returned neutrons, 2. The spontaneous fission, 3. The extrapolation from the tail of the fission spectrum to the zero pulse height, 4. The anisotropy of the fission fragments, 5. The self-absorption of the fission fragments in the samples, 6. The impurities in the samples, 7. The chamber- and the target-scattered neutrons, 8. The parasitic neutrons, 9. The attenuation of the incident neutron flux by the backing plates, 10. The difference in the solid angle subtended by the samples to the target between the 235U sample and another one. .Corrections are for U-235 : Room-Returned Neutrons 1.5 - 4.7% Extrapolation 0.2 - 1.5% Self-absorption 2.4 - 2.5% Sample impurity 0.1% ERR-ANALYS (ERR-1) Error due to the number of U-235 atoms (ERR-2) Error due to the sample number of atoms (ERR-3) Max error of the fission rate ratio (ERR-4) Max error due to the correction factor (ERR-T) Max total error evaluated by considering correlations among the various errors Minimum errors are given in the Table III of main reference (MONIT-ERR) Error of the U-235 monitor HISTORY (20080204C) SM ENDBIB 77 COMMON 2 3 ERR-1 MONIT-ERR PER-CENT PER-CENT 1.47 4. ENDCOMMON 3 ENDSUBENT 84 SUBENT 22282002 20080204 20080402 20080318 2192 BIB 5 20 REACTION ((90-TH-232(N,F),,SIG)/(92-U-235(N,F),,SIG)) SAMPLE .Sample Th-232 has arial density 171.3 microgram/cm2. Sample content ==> Element content,% number of atoms Th-232 100. (20.41+-0.33)E17; Th-230 0.00001 0.0001E+17; CORRECTION .Corrections are for - Room-Returned Neutrons <=O.l % Extrapolation 0.5 - 1.8% Self-absorption 2.9 - 3.0% Chamber-scatterd neutrons 0.6 - 0.7% Target-scatterd neutrons 0.5 - 0,7% COVARIANCE .Correlation matrix for ratio values Energy Matrix times 100 ------ ---------------- 13.47 100 14.09 87 100 14.46 86 87 100 14.89 87 87 87 100 STATUS (TABLE) Table IV-I page 112 of main reference ENDBIB 20 COMMON 3 3 ERR-2 ERR-3 ERR-4 PER-CENT PER-CENT PER-CENT 1.64 0.887 0.276 ENDCOMMON 3 DATA 5 4 EN EN-ERR DATA ERR-T ERR-T MEV MEV NO-DIM NO-DIM PER-CENT 13.47 0.18 0.150 0.004 2.41 14.00 0.06 0.158 0.004 2.38 14.46 0.16 0.166 0.004 2.37 14.89 0.29 0.181 0.004 2.38 ENDDATA 6 ENDSUBENT 35 SUBENT 22282003 20080204 20080402 20080318 2192 BIB 5 25 REACTION ((92-U-233(N,F),,SIG)/(92-U-235(N,F),,SIG)) SAMPLE .Sample U-233 has arial density 129.9 microgram/cm2. Sample content ==> Element content,% number of atoms U-232 0.0003 0.00005E+17; U-233 99.47 (14.41+-0.07)E+17 U-234 0.166 0.024E+17; U-235 0.064 0.009E+17; U-236 0.015 0.002E+17; U-238 0.282 0.041E+17; CORRECTION .Corrections are for - Room-Returned Neutrons 2.1 - 3.9% Extrapolation 1.9 - 3.7% Self-absorption 2.7% Sample impurity 0.3% Chamber-scatterd neutrons 0.3% Target-scatterd neutrons 0,3% COVARIANCE .Correlation matrix for ratio values Energy Matrix times 100 ------ ---------------- 13.47 100 14.09 81 100 14.46 79 81 100 14.89 78 80 79 100 STATUS (TABLE) Table V-1 page 114 of main reference ENDBIB 25 COMMON 3 3 ERR-2 ERR-3 ERR-4 PER-CENT PER-CENT PER-CENT 0.487 1.51 0.131 ENDCOMMON 3 DATA 5 4 EN EN-ERR DATA ERR-T ERR-T MEV MEV NO-DIM NO-DIM PER-CENT 13.47 0.18 1.18 0.03 2.19 14.00 0.06 1.19 0.03 2.17 14.46 0.16 1.19 0.02 2.13 14.89 0.29 1.14 0.02 2.04 ENDDATA 6 ENDSUBENT 40 SUBENT 22282004 20080204 20080402 20080318 2192 BIB 5 25 REACTION ((92-U-234(N,F),,SIG)/(92-U-235(N,F),,SIG)) SAMPLE .Sample U-234 has arial density 136.0 microgram/cm2. Sample content ==> Element content,% number of atoms U-232 0.003 0.0004 E+17; U-233 0.0004 0.00005E+17; U-234 99.08 (14.97+-0.09)E+17; U-235 0.078 0.012E+17; U-236 0.055 0.008E+17; U-238 0.786 0.119E+17; CORRECTION .Corrections are for - Room-Returned Neutrons <=0.1% Extrapolation 1.4 - 3.1% Self-absorption 2.7 - 2.8% Sample impurity 0.5 - 0.6% Chamber-scatterd neutrons 0.0% Target-scatterd neutrons 0.1 - 0.2% COVARIANCE .Correlation matrix for ratio values Energy Matrix times 100 ------ ---------------- 13.47 100 14.09 76 100 14.46 78 77 100 14.89 75 76 77 100 STATUS (TABLE) Table VI-1 page 115 of main reference ENDBIB 25 COMMON 3 3 ERR-2 ERR-3 ERR-4 PER-CENT PER-CENT PER-CENT 0.597 1.41 0.160 ENDCOMMON 3 DATA 5 4 EN EN-ERR DATA ERR-T ERR-T MEV MEV NO-DIM NO-DIM PER-CENT 13.47 0.18 1.00 0.02 2.15 14.00 0.06 0.983 0.02 1.99 14.46 0.16 0.999 0.02 2.03 14.89 0.29 1.01 0.02 1.96 ENDDATA 6 ENDSUBENT 40 SUBENT 22282005 20080204 20080402 20080318 2192 BIB 5 24 REACTION ((92-U-236(N,F),,SIG)/(92-U-235(N,F),,SIG)) SAMPLE .Sample U-236 has arial density 101.5 microgram/cm2. Sample content ==> Element content,% number of atoms U-233 0.002 0.0002E+17; U-234 0.124 0.014 E+17 U-235 9.403 1.053E+17; U-236 89.13 (9.981+-0.167)E+17; U-238 1.786 0.151E+17; CORRECTION .Corrections are for - Room-Returned Neutrons 0.3 - 0.6% Extrapolation 0.2 - 0.8% Self-absorption 2.5 - 2.6% Sample impurity 12.6 -13.3% Chamber-scatterd neutrons 0.3 - 0.4% Target-scatterd neutrons 0.3 - 0.5% COVARIANCE .Correlation matrix for ratio values Energy Matrix times 100 ------ ---------------- 13.47 100 14.09 74 100 14.46 73 74 100 14.89 73 74 74 100 STATUS (TABLE) Table VII-1 page 117 of main reference ENDBIB 24 COMMON 3 3 ERR-2 ERR-3 ERR-4 PER-CENT PER-CENT PER-CENT 1.68 0.965 0.897 ENDCOMMON 3 DATA 5 4 EN EN-ERR DATA ERR-T ERR-T MEV MEV NO-DIM NO-DIM PER-CENT 13.47 0.18 0.756 0.018 2.36 14.00 0.06 0.786 0.018 1.33 14.46 0.16 0.797 0.019 2.34 14.89 0.29 0.803 0.019 1.34 ENDDATA 6 ENDSUBENT 39 SUBENT 22282006 20080204 20080402 20080318 2192 BIB 5 22 REACTION ((92-U-238(N,F),,SIG)/(92-U-235(N,F),,SIG)) SAMPLE .Sample U-238 has arial density 108.0 microgram/cm2. Sample content ==> Element content,% number of atoms U-234 0.0003 0.00004E+17 U-235 0.037 0.004E+17; U-238 99.96 (11.82+-0.19)E+17; CORRECTION .Corrections are for - Room-Returned Neutrons <=0.1% Extrapolation 0.2 - 0.9% Self-absorption 2.5 - 2.6% Sample impurity 0.1% Chamber-scatterd neutrons 0.5 - 0.7% Target-scatterd neutrons 0.4 - 0.7% COVARIANCE .Correlation matrix for ratio values Energy Matrix times 100 ------ ---------------- 13.47 100 14.09 78 100 14.46 78 78 100 14.89 78 78 78 100 STATUS (TABLE) Table VIII-1 page 118 of main reference ENDBIB 22 COMMON 3 3 ERR-2 ERR-3 ERR-4 PER-CENT PER-CENT PER-CENT 1.57 0.923 0.271 ENDCOMMON 3 DATA 5 4 EN EN-ERR DATA ERR-T ERR-T MEV MEV NO-DIM NO-DIM PER-CENT 13.47 0.18 0.544 0.011 2.02 14.00 0.06 0.560 0.011 2.00 14.46 0.16 0.572 0.011 2.01 14.89 0.29 0.584 0.012 2.01 ENDDATA 6 ENDSUBENT 37 SUBENT 22282007 20080204 20080402 20080318 2192 BIB 5 21 REACTION ((93-NP-237(N,F),,SIG)/(92-U-235(N,F),,SIG)) SAMPLE .Sample NP-237 has arial density 90.88 microgram/cm2. Sample content ==> Element content,% number of atoms Np-237 100.03 (9.985+-0.066)E+17 Pu-238 0.0002 0.00002E+17; CORRECTION .Corrections are for - Room-Returned Neutrons <=0.1% Extrapolation 0.3 - 1.1% Self-absorption 2.4 - 2.4% Sample impurity 0.0% Chamber-scatterd neutrons 0.0% Target-scatterd neutrons 0.1 - 0.2% COVARIANCE .Correlation matrix for ratio values Energy Matrix times 100 ------ ---------------- 13.47 100 14.09 70 100 14.46 71 72 100 14.89 70 72 72 100 STATUS (TABLE) Table IX-1 page 120 of main reference ENDBIB 21 COMMON 3 3 ERR-2 ERR-3 ERR-4 PER-CENT PER-CENT PER-CENT 0.661 1.04 0.168 ENDCOMMON 3 DATA 5 4 EN EN-ERR DATA ERR-T ERR-T MEV MEV NO-DIM NO-DIM PER-CENT 13.47 0.18 1.11 0.02 1.94 14.00 0.06 1.06 0.02 1.91 14.46 0.16 1.08 0.02 1.90 14.89 0.29 1.07 0.02 1.90 ENDDATA 6 ENDSUBENT 36 SUBENT 22282008 20080204 20080402 20080318 2192 BIB 5 25 REACTION ((94-PU-242(N,F),,SIG)/(92-U-235(N,F),,SIG)) SAMPLE .Sample PU-242 has arial density 10.46 microgram/cm2. Sample content ==> Element content,% number of atoms PU-238 0.003 0.00003E+17; PU-239 0.019 0.0002 E+17; PU-240 0.083 0.0009 E+17; PU-241 0.043 0.0005 E+17; PU-242 99.84 (1.126+-0.09)E+17; AM-241 0.013 0.0001 E+17; CORRECTION .Corrections are for - Room-Returned Neutrons <=0.1% Spontaneous fission 2.4 - 2.6% Extrapolation 0.1 - 0.6% Self-absorption 1.9% Sample impurity 0.2% Chamber-scatterd neutrons <=0.1% Target-scatterd neutrons 0.1 - 0.2% COVARIANCE .Correlation matrix for ratio values Energy Matrix times 100 ------ ---------------- 14.09 100 14.46 83 100 14.89 84 84 100 STATUS (TABLE) Table X-1 page 121 of main reference ENDBIB 25 COMMON 3 3 ERR-2 ERR-3 ERR-4 PER-CENT PER-CENT PER-CENT 0.816 0.825 0.151 ENDCOMMON 3 DATA 5 3 EN EN-ERR DATA ERR-T ERR-T MEV MEV NO-DIM NO-DIM PER-CENT 14.00 0.06 0.998 0.019 1.86 14.46 0.16 1.00 0.02 1.89 14.89 0.29 0.989 0.018 1.87 ENDDATA 5 ENDSUBENT 39 SUBENT 22282009 20080204 20080402 20080318 2192 BIB 5 24 REACTION ((95-AM-243(N,F),,SIG)/(92-U-235(N,F),,SIG)) SAMPLE .Sample Am-243 has arial density 20.33 microgram/cm2. Sample content ==> Element content,% number of atoms PU-239 0.041 0.0009 E+17; PU-240 0.054 0.001 E+17; Am-241 0.023 0.0005 E+17; Am-243 99.59 (2.176+-0.045)E+17; Cm-244 0.290 0.006 E+17; CORRECTION .Corrections are for - Room-Returned Neutrons <=0.1% Spontaneous fission 38.9 -43.7% Extrapolation 1.0 - 2.4% Self-absorption 1.9 - 2.0% Sample impurity 0.5% Chamber-scatterd neutrons <=0.1% Target-scatterd neutrons <=0.2% COVARIANCE .Correlation matrix for ratio values Energy Matrix times 100 ------ ---------------- 14.09 100 14.46 89 100 14.89 89 89 100 STATUS (TABLE) Table XI-1 page 123 of main reference ENDBIB 24 COMMON 3 3 ERR-2 ERR-3 ERR-4 PER-CENT PER-CENT PER-CENT 2.08 0.945 0.170 ENDCOMMON 3 DATA 5 3 EN EN-ERR DATA ERR-T ERR-T MEV MEV NO-DIM NO-DIM PER-CENT 14.00 0.06 1.08 0.03 2.47 14.46 0.16 1.05 0.03 2.46 14.89 0.29 1.06 0.03 2.46 ENDDATA 5 ENDSUBENT 38 SUBENT 22282010 20080204 20080402 20080318 2192 BIB 5 12 REACTION (90-TH-232(N,F),,SIG) MONITOR (92-U-235(N,F),,SIG) MONIT-REF .ENDF/B-V COVARIANCE .Correlation matrix for sigma values Energy Matrix times 100 ------ ---------------- 13.47 100 14.09 97 100 14.46 96 97 100 14.89 97 97 97 100 STATUS (TABLE) Table IV-2 page 113 of main reference (DEP,22282002) ENDBIB 12 COMMON 3 3 ERR-2 ERR-3 ERR-4 PER-CENT PER-CENT PER-CENT 1.64 0.887 0.276 ENDCOMMON 3 DATA 5 4 EN EN-ERR DATA ERR-T ERR-T MEV MEV B B PER-CENT 13.47 0.18 0.300 0.014 4.67 14.00 0.06 0.327 0.015 4.65 14.46 0.16 0.348 0.016 4.65 14.89 0.29 0.380 0.018 4.65 ENDDATA 6 ENDSUBENT 27 SUBENT 22282011 20080204 20080402 20080318 2192 BIB 5 12 REACTION (92-U-233(N,F),,SIG) MONITOR (92-U-235(N,F),,SIG) MONIT-REF .ENDF/B-V COVARIANCE .Correlation matrix for sigma values Energy Matrix times 100 ------ ---------------- 13.47 100 14.09 96 100 14.46 95 96 100 14.89 95 96 95 100 STATUS (TABLE) Table V-2 page 114 of main reference (DEP,22282003) ENDBIB 12 COMMON 3 3 ERR-2 ERR-3 ERR-4 PER-CENT PER-CENT PER-CENT 0.487 1.51 0.131 ENDCOMMON 3 DATA 5 4 EN EN-ERR DATA ERR-T ERR-T MEV MEV B B PER-CENT 13.47 0.18 2.35 0.11 4.56 14.00 0.06 2.46 0.11 4.55 14.46 0.16 2.41 0.11 4.53 14.89 0.29 2.39 0.11 4.49 ENDDATA 6 ENDSUBENT 27 SUBENT 22282012 20080204 20080402 20080318 2192 BIB 5 12 REACTION (92-U-234(N,F),,SIG) MONITOR (92-U-235(N,F),,SIG) MONIT-REF .ENDF/B-V COVARIANCE .Correlation matrix for sigma values Energy Matrix times 100 ------ ---------------- 13.47 100 14.09 95 100 14.46 95 95 100 14.89 95 95 95 100 STATUS (TABLE) Table VI-2 page 116 of main reference (DEP,22282004) ENDBIB 12 COMMON 3 3 ERR-2 ERR-3 ERR-4 PER-CENT PER-CENT PER-CENT 0.597 1.41 0.160 ENDCOMMON 3 DATA 5 4 EN EN-ERR DATA ERR-T ERR-T MEV MEV B B PER-CENT 13.47 0.18 2.00 0.09 4.54 14.00 0.06 2.03 0.09 4.47 14.46 0.16 2.03 0.09 4.48 14.89 0.29 2.13 0.10 4.46 ENDDATA 6 ENDSUBENT 27 SUBENT 22282013 20080204 20080402 20080318 2192 BIB 5 12 REACTION (92-U-236(N,F),,SIG) MONITOR (92-U-235(N,F),,SIG) MONIT-REF .ENDF/B-V COVARIANCE .Correlation matrix for sigma values Energy Matrix times 100 ------ ---------------- 13.47 100 14.09 93 100 14.46 93 93 100 14.89 93 93 03 100 STATUS (TABLE) Table VII-2 page 117 of main reference (DEP,22282005) ENDBIB 12 COMMON 3 3 ERR-2 ERR-3 ERR-4 PER-CENT PER-CENT PER-CENT 1.68 0.965 0.897 ENDCOMMON 3 DATA 5 4 EN EN-ERR DATA ERR-T ERR-T MEV MEV B B PER-CENT 13.47 0.18 1.51 0.07 4.64 14.00 0.06 1.63 0.08 4.63 14.46 0.16 1.70 0.08 4.64 14.89 0.29 1.69 0.08 4.63 ENDDATA 6 ENDSUBENT 27 SUBENT 22282014 20080204 20080402 20080318 2192 BIB 5 11 REACTION (92-U-238(N,F),,SIG) MONITOR (92-U-235(N,F),,SIG) MONIT-REF .ENDF/B-V COVARIANCE .Correlation matrix for sigma values Energy Matrix times 100 ------ ---------------- 13.47 100 14.09 96 100 14.46 96 96 100 14.89 96 96 96 100 STATUS (TABLE) Table VIII-2 page 119 of main reference ENDBIB 11 COMMON 3 3 ERR-2 ERR-3 ERR-4 PER-CENT PER-CENT PER-CENT 1.57 0.923 0.271 ENDCOMMON 3 DATA 5 4 EN EN-ERR DATA ERR-T ERR-T MEV MEV B B PER-CENT 13.47 0.18 1.08 0.05 4.48 14.00 0.06 1.16 0.05 4.47 14.46 0.16 1.20 0.05 4.48 14.89 0.29 1.23 0.05 4.47 ENDDATA 6 ENDSUBENT 26 SUBENT 22282015 20080204 20080402 20080318 2192 BIB 5 12 REACTION (93-NP-237(N,F),,SIG) MONITOR (92-U-235(N,F),,SIG) MONIT-REF .ENDF/B-V COVARIANCE .Correlation matrix for sigma values Energy Matrix times 100 ------ ---------------- 13.47 100 14.09 94 100 14.46 94 95 100 14.89 94 95 95 100 STATUS (TABLE) Table IX-2 page 120 of main reference (DEP,22282007) ENDBIB 12 COMMON 3 3 ERR-2 ERR-3 ERR-4 PER-CENT PER-CENT PER-CENT 0.661 1.04 0.168 ENDCOMMON 3 DATA 5 4 EN EN-ERR DATA ERR-T ERR-T MEV MEV B B PER-CENT 13.47 0.18 2.21 0.10 4.45 14.00 0.06 2.18 0.10 4.43 14.46 0.16 2.25 0.10 4.43 14.89 0.29 2.26 0.10 4.43 ENDDATA 6 ENDSUBENT 27 SUBENT 22282016 20080204 20080402 20080318 2192 BIB 5 11 REACTION (94-PU-242(N,F),,SIG) MONITOR (92-U-235(N,F),,SIG) MONIT-REF .ENDF/B-V COVARIANCE .Correlation matrix for sigma values Energy Matrix times 100 ------ ---------------- 14.09 100 14.46 97 100 14.89 97 97 100 STATUS (TABLE) Table X-2 page 122 of main reference (DEP,22282008) ENDBIB 11 COMMON 3 3 ERR-2 ERR-3 ERR-4 PER-CENT PER-CENT PER-CENT 0.816 0.825 0.151 ENDCOMMON 3 DATA 5 3 EN EN-ERR DATA ERR-T ERR-T MEV MEV B B PER-CENT 14.00 0.06 2.06 0.09 4.41 14.46 0.16 2.10 0.09 4.42 14.89 0.29 2.08 0.09 4.41 ENDDATA 5 ENDSUBENT 25 SUBENT 22282017 20080204 20080402 20080318 2192 BIB 5 10 REACTION (95-AM-243(N,F),,SIG) MONITOR (92-U-235(N,F),,SIG) MONIT-REF .ENDF/B-V COVARIANCE .Correlation matrix for sigma values Energy Matrix times 100 ------ ---------------- 14.09 100 14.46 97 100 14.89 97 97 100 STATUS (TABLE) Table XI-2 page 123 of main reference ENDBIB 10 COMMON 3 3 ERR-2 ERR-3 ERR-4 PER-CENT PER-CENT PER-CENT 2.08 0.945 0.170 ENDCOMMON 3 DATA 5 3 EN EN-ERR DATA ERR-T ERR-T MEV MEV B B PER-CENT 14.00 0.06 2.23 0.11 4.70 14.46 0.16 2.21 0.10 4.69 14.89 0.29 2.22 0.10 4.69 ENDDATA 5 ENDSUBENT 24