ENTRY 20036 20230129 231320036 0 1 SUBENT 20036001 20230129 231320036 1 1 BIB 15 61 20036 1 2 TITLE Neutron scattering by U-235 and Pu-239 for incident 20036 1 3 neutrons of 2, 3 and 4 MeV 20036 1 4 INSTITUTE (2UK ALD) 20036 1 5 REFERENCE (R,AWRE-O-55/69,1969) 20036 1 6 AUTHOR (R.Batchelor, K.Wyld) 20036 1 7 FACILITY (VDG,2UK ALD) 6 MV Van de Graaff, terminal pulsing and 20036 1 8 bunching (Klystron). 20036 1 9 INC-SOURCE (P-T) 20036 1 10 The incident energies, 2, 3 and 4 MeV are nominal but 20036 1 11 are correct within the limits of the overall neutron 20036 1 12 energy spreads which are about +- 50 keV. 20036 1 13 SAMPLE The samples were hollow cylinders. nominally 20036 1 14 2 in. high, 1 in. outer diam. and 0.65 in. inner 20036 1 15 diam., and were canned in aluminium of total wall 20036 1 16 thickness 0.020 in. 20036 1 17 METHOD (TOF) flight path = 1.74 m. The resolution of the 20036 1 18 time-of-flight spectrometer was about 5 nanosec. 20036 1 19 DETECTOR (SCIN) Liquid scintillator detector. 20036 1 20 ANALYSIS The differential cross-sections were estimated 20036 1 21 by interpolating each continuous non-elastic spectrum 20036 1 22 underneath the elastic 'peak' and subtracting to give 20036 1 23 counts in the peak. The peak counts represent 20036 1 24 only true elastic.(If the excitation of low lying 20036 1 25 levels is not enhanced by direct interactions.) 20036 1 26 The continuous non-elastic time spectra are converted 20036 1 27 to energy spectra in histogram form, each energy band 20036 1 28 corresponding roughly to one resolution width. 20036 1 29 Cross sections were calculated on the assumption that 20036 1 30 the samples consisted of one isotope only. This is not20036 1 31 expected to lead to a large error since the (n,n') 20036 1 32 cross section and spectra of various isotopes are not 20036 1 33 likely to be very different. 20036 1 34 MONITOR (1-H-1(N,EL)1-H-1,,SIG) A polythene sample was used to20036 1 35 relate cross sections to the hydrogen scattering cross20036 1 36 section. 20036 1 37 COMMENT The secondary energy spectra for U-235 and Pu-239 have20036 1 38 been analysed into fission and inelastic components, 20036 1 39 the analysis showing possible evidence that the 20036 1 40 fission component is a little harder than anticipated.20036 1 41 Because of this uncertainty about the fission 20036 1 42 component, the shape of the inelastic component is not20036 1 43 very reliable. 20036 1 44 CORRECTION In calculating cross sections, corrections were made 20036 1 45 for flux attenuation. 20036 1 46 ERR-ANALYS (DATA-ERR) The errors on the spectra are about 5% and 20036 1 47 arise from 20036 1 48 * errors in the knowledge of the backgrounds, 20036 1 49 * errors in the detector efficiency calibration and 20036 1 50 * errors in the time calibration. 20036 1 51 At the very low energies, in the region below about 20036 1 52 600 keV, the errors on the individual steps exceed 20036 1 53 5% and are not easy to determine precisely. 20036 1 54 HISTORY (19710202C) 20036 1 55 (19810121A) Correction of DATA-dimensions and DATA-ERR 20036 1 56 section moved to COMMON in some Subents. 20036 1 57 (19860311U) N.Ch 20036 1 58 (19860620U) HH in Subent 006 20036 1 59 (20190117A) SD:Updated to new date formats,lower case. 20036 1 60 Subents 002-004; 006-008; 009-011; 012-014; 016-018; 20036 1 61 019-021 were merged. 20036 1 62 (20230129A) SD: Corrections in several Subents. 20036 1 63 ENDBIB 61 0 20036 1 64 COMMON 1 3 20036 1 65 EN-RSL 20036 1 66 MEV 20036 1 67 0.05 20036 1 68 ENDCOMMON 3 0 20036 1 69 ENDSUBENT 68 0 20036 199999 SUBENT 20036002 20230129 231320036 2 1 BIB 6 13 20036 2 2 REACTION (92-U-235(N,EL)92-U-235,EXL,DA) 20036 2 3 SAMPLE 92.6% U-235. 20036 2 4 REL-REF (C,,S.Simakov+,S,INDC(NDS)-0857,91,2022) 20036 2 5 CRITIQUE S.Simakov (2022-08-06): Possible inclusion of inelastic20036 2 6 scattering below Ex~0.55 MeV at 2 and 3 MeV, 20036 2 7 1.25 MeV at 4 MeV 20036 2 8 STATUS (TABLE) Data from table 1 of AWRE-O-55/69. 20036 2 9 HISTORY (19810121A) 20036 2 10 (20190117A) SD: Data from Subents 003, 004 added. 20036 2 11 STATUS updated. COS -> ANG according to presentation 20036 2 12 in the table. 20036 2 13 (20230129A) SD: CRITIQUE, REL-REF added. SF5=EXL added 20036 2 14 to REACTION code. 20036 2 15 ENDBIB 13 0 20036 2 16 NOCOMMON 0 0 20036 2 17 DATA 4 27 20036 2 18 EN ANG DATA DATA-ERR 20036 2 19 MEV ADEG B/SR B/SR 20036 2 20 2. 30. 1.23 0.06 20036 2 21 2. 40. 0.650 0.035 20036 2 22 2. 50. 0.217 0.011 20036 2 23 2. 60. 0.091 0.009 20036 2 24 2. 75. 0.143 0.009 20036 2 25 2. 90. 0.208 0.011 20036 2 26 2. 105. 0.166 0.009 20036 2 27 2. 120. 0.115 0.009 20036 2 28 2. 135. 0.069 0.009 20036 2 29 3. 30. 1.51 0.08 20036 2 30 3. 40. 0.558 0.033 20036 2 31 3. 50. 0.149 0.011 20036 2 32 3. 60. 0.110 0.010 20036 2 33 3. 75. 0.152 0.011 20036 2 34 3. 90. 0.151 0.011 20036 2 35 3. 105. 0.063 0.010 20036 2 36 3. 120. 0.022 0.010 20036 2 37 3. 135. 0.024 0.010 20036 2 38 4. 30. 1.23 0.06 20036 2 39 4. 40. 0.396 0.028 20036 2 40 4. 50. 0.106 0.010 20036 2 41 4. 60. 0.041 0.010 20036 2 42 4. 75. 0.100 0.010 20036 2 43 4. 90. 0.101 0.010 20036 2 44 4. 105. 0.038 0.010 20036 2 45 4. 120. 0.022 0.010 20036 2 46 4. 135. 0.050 0.010 20036 2 47 ENDDATA 29 0 20036 2 48 ENDSUBENT 47 0 20036 299999 NOSUBENT 20036003 20190117 227420036 3 1 NOSUBENT 20036004 20190117 227420036 4 1 SUBENT 20036005 20190117 227420036 5 1 BIB 7 11 20036 5 2 REACTION (92-U-235(N,INL)92-U-235,,SIG) 20036 5 3 estimated. 20036 5 4 SAMPLE 92.6% U-235. 20036 5 5 ANALYSIS The assumption that the shape of the (n,n') cross- 20036 5 6 section is given by n(E) = B * exp(-E/t) was used. 20036 5 7 CORRECTION For, multiple scattering in the samples by an 20036 5 8 extension of the method by Cranberg (see REL-REF) 20036 5 9 REL-REF (M,,L.Cranberg,R,LA-2177,1959) 20036 5 10 STATUS (TABLE) Data from table 5 of AWRE-O-55/69. 20036 5 11 HISTORY (19810121A) 20036 5 12 (20190117U) SD: STATUS updated. 20036 5 13 ENDBIB 11 0 20036 5 14 COMMON 1 3 20036 5 15 EN-RSL 20036 5 16 MEV 20036 5 17 0.05 20036 5 18 ENDCOMMON 3 0 20036 5 19 DATA 3 3 20036 5 20 EN DATA DATA-ERR 20036 5 21 MEV B B 20036 5 22 2. 2.00 0.38 20036 5 23 3. 2.39 0.36 20036 5 24 4. 2.10 0.35 20036 5 25 ENDDATA 5 0 20036 5 26 ENDSUBENT 25 0 20036 599999 SUBENT 20036006 20230129 231320036 6 1 BIB 6 14 20036 6 2 REACTION (92-U-235(N,INL)92-U-235,,DE) 20036 6 3 SAMPLE 92.6% U-235. 20036 6 4 ANALYSIS Inelastic neutron spectra were obtained by subtraction20036 6 5 of the fission spectra from the non-elastic spectra. 20036 6 6 The fission spectra are represented by 20036 6 7 (a * square root (E) * exp(-B * E)). 20036 6 8 REL-REF (M,,J.Terrell,J,PR,113,527,1959) 20036 6 9 STATUS (TABLE) data taken from table 3 of AWRE-O-55/69. 20036 6 10 (DEP,20036009) Dependent of non-elastic data 20036 6 11 HISTORY (19810121A) 20036 6 12 (19860311U)N.Ch 20036 6 13 (19860620U)HH data heading corrected 20036 6 14 (20190117A) SD: Data from Subents 007,008 added. 20036 6 15 (20230129A) SD: E-EXC-MIN/MAX -> E-MIN/MAX. 20036 6 16 ENDBIB 14 0 20036 6 17 COMMON 1 3 20036 6 18 DATA-ERR 20036 6 19 PER-CENT 20036 6 20 5. 20036 6 21 ENDCOMMON 3 0 20036 6 22 DATA 4 42 20036 6 23 EN E-MAX E-MIN DATA 20036 6 24 MEV MEV MEV B/MEV 20036 6 25 2. 0.473 0.386 1.52 20036 6 26 2. 0.566 0.473 1.80 20036 6 27 2. 0.687 0.566 1.80 20036 6 28 2. 0.807 0.687 1.73 20036 6 29 2. 0.904 0.807 1.51 20036 6 30 2. 1.022 0.904 1.13 20036 6 31 2. 1.162 1.022 0.75 20036 6 32 2. 1.243 1.162 0.63 20036 6 33 2. 1.333 1.243 0.52 20036 6 34 2. 1.429 1.333 0.53 20036 6 35 3. 0.504 0.409 1.88 20036 6 36 3. 0.604 0.504 1.97 20036 6 37 3. 0.704 0.604 1.76 20036 6 38 3. 0.827 0.704 1.48 20036 6 39 3. 0.929 0.827 1.41 20036 6 40 3. 1.051 0.929 1.06 20036 6 41 3. 1.197 1.051 0.83 20036 6 42 3. 1.283 1.197 0.64 20036 6 43 3. 1.373 1.283 0.49 20036 6 44 3. 1.483 1.378 0.50 20036 6 45 3. 1.602 1.483 0.44 20036 6 46 3. 1.735 1.602 0.41 20036 6 47 3. 1.886 1.735 0.31 20036 6 48 3. 2.056 1.886 0.32 20036 6 49 3. 2.251 2.056 0.29 20036 6 50 4. 0.554 0.445 1.78 20036 6 51 4. 0.639 0.554 1.74 20036 6 52 4. 0.746 0.639 1.64 20036 6 53 4. 0.832 0.746 1.35 20036 6 54 4. 0.935 0.832 0.92 20036 6 55 4. 1.057 0.935 0.86 20036 6 56 4. 1.128 1.057 0.70 20036 6 57 4. 1.206 1.128 0.57 20036 6 58 4. 1.292 1.206 0.48 20036 6 59 4. 1.388 1.292 0.44 20036 6 60 4. 1.495 1.388 0.34 20036 6 61 4. 1.610 1.495 0.30 20036 6 62 4. 1.750 1.610 0.23 20036 6 63 4. 1.902 1.750 0.23 20036 6 64 4. 2.070 1.902 0.18 20036 6 65 4. 2.273 2.070 0.15 20036 6 66 4. 2.500 2.273 0.17 20036 6 67 ENDDATA 44 0 20036 6 68 ENDSUBENT 67 0 20036 699999 NOSUBENT 20036007 20190117 227420036 7 1 NOSUBENT 20036008 20190117 227420036 8 1 SUBENT 20036009 20230129 231320036 9 1 BIB 4 7 20036 9 2 REACTION (92-U-235(N,X)0-NN-1,EM,DE) 20036 9 3 SAMPLE 92.6% U-235. 20036 9 4 STATUS (TABLE) Data from table 3 of AWRE-O-55/69. 20036 9 5 HISTORY (19810121A) 20036 9 6 (20190117A) SD: SF3=NON -> X; SF4=NN-1 and SF5=EM added20036 9 7 to REACTION code. Data from Subents 010,011 added. 20036 9 8 (20230129A) SD: E-EXC-MIN/MAX -> E-MIN/MAX. 20036 9 9 ENDBIB 7 0 20036 9 10 COMMON 1 3 20036 9 11 DATA-ERR 20036 9 12 PER-CENT 20036 9 13 5. 20036 9 14 ENDCOMMON 3 0 20036 9 15 DATA 4 60 20036 9 16 EN E-MAX E-MIN DATA 20036 9 17 MEV MEV MEV B/MEV 20036 9 18 2. 0.473 0.386 2.67 20036 9 19 2. 0.566 0.473 2.97 20036 9 20 2. 0.687 0.566 2.98 20036 9 21 2. 0.807 0.687 2.81 20036 9 22 2. 0.904 0.807 2.68 20036 9 23 2. 1.022 0.904 2.28 20036 9 24 2. 1.162 1.022 1.86 20036 9 25 2. 1.243 1.162 1.70 20036 9 26 2. 1.333 1.243 1.57 20036 9 27 2. 1.429 1.333 1.56 20036 9 28 2. 2.331 1.429 0.76 20036 9 29 2. 2.587 2.331 0.78 20036 9 30 2. 2.866 2.587 0.60 20036 9 31 2. 3.190 2.866 0.51 20036 9 32 2. 3.574 3.190 0.42 20036 9 33 2. 4.033 3.574 0.31 20036 9 34 2. 4.584 4.033 0.22 20036 9 35 2. 5.257 4.584 0.15 20036 9 36 2. 6.092 5.257 0.08 20036 9 37 3. 0.504 0.409 3.00 20036 9 38 3. 0.604 0.504 3.11 20036 9 39 3. 0.704 0.604 2.90 20036 9 40 3. 0.827 0.704 2.62 20036 9 41 3. 0.929 0.827 2.43 20036 9 42 3. 1.051 0.929 2.14 20036 9 43 3. 1.197 1.051 1.85 20036 9 44 3. 1.283 1.197 1.62 20036 9 45 3. 1.373 1.283 1.46 20036 9 46 3. 1.483 1.378 1.42 20036 9 47 3. 1.602 1.483 1.31 20036 9 48 3. 1.735 1.602 1.23 20036 9 49 3. 1.886 1.735 1.09 20036 9 50 3. 2.056 1.886 1.04 20036 9 51 3. 2.251 2.056 0.94 20036 9 52 3. 2.460 2.251 0.90 20036 9 53 3. 3.727 2.460 0.58 20036 9 54 3. 4.267 3.727 0.29 20036 9 55 3. 4.871 4.267 0.17 20036 9 56 3. 5.611 4.871 0.10 20036 9 57 3. 6.534 5.611 0.05 20036 9 58 4. 0.554 0.445 2.80 20036 9 59 4. 0.639 0.554 2.79 20036 9 60 4. 0.746 0.639 2.70 20036 9 61 4. 0.832 0.746 2.40 20036 9 62 4. 0.935 0.832 2.25 20036 9 63 4. 1.057 0.935 1.87 20036 9 64 4. 1.128 1.057 1.68 20036 9 65 4. 1.206 1.128 1.54 20036 9 66 4. 1.292 1.206 1.42 20036 9 67 4. 1.388 1.292 1.34 20036 9 68 4. 1.495 1.388 1.21 20036 9 69 4. 1.610 1.495 1.12 20036 9 70 4. 1.750 1.610 1.02 20036 9 71 4. 1.902 1.750 0.96 20036 9 72 4. 2.070 1.902 0.86 20036 9 73 4. 2.273 2.070 0.77 20036 9 74 4. 2.500 2.273 0.72 20036 9 75 4. 2.744 2.500 0.64 20036 9 76 4. 5.208 2.744 0.26 20036 9 77 4. 6.144 5.208 0.07 20036 9 78 ENDDATA 62 0 20036 9 79 ENDSUBENT 78 0 20036 999999 NOSUBENT 20036010 20190117 227420036 10 1 NOSUBENT 20036011 20190117 227420036 11 1 SUBENT 20036012 20230129 231320036 12 1 BIB 6 14 20036 12 2 REACTION (94-PU-239(N,EL)94-PU-239,EXL,DA) 20036 12 3 SAMPLE 93.63% Pu-239, 5.86% Pu-240, 0.51% Pu-241, 20036 12 4 stabilized with 1.2% gallium. 20036 12 5 REL-REF (C,,S.Simakov+,S,INDC(NDS)-0857,91,2022) 20036 12 6 CRITIQUE S.Simakov (2022-08-06): Possible inclusion of inelastic20036 12 7 scattering below Ex~0.55 MeV at 2 and 3 MeV, 20036 12 8 1.25 MeV at 4 MeV 20036 12 9 STATUS (TABLE) Data from table 2 of AWRE-O-55/69. 20036 12 10 HISTORY (19810121A) 20036 12 11 (20190117A) SD: Data from Subents 013, 014 added. 20036 12 12 STATUS updated. COS -> ANG according to presentation 20036 12 13 in the table. 20036 12 14 (20230129A) SD: CRITIQUE, REL-REF added. SF5=EXL added 20036 12 15 to REACTION code. 20036 12 16 ENDBIB 14 0 20036 12 17 NOCOMMON 0 0 20036 12 18 DATA 4 27 20036 12 19 EN ANG DATA DATA-ERR 20036 12 20 MEV ADEG B/SR B/SR 20036 12 21 2. 30. 1.170 0.060 20036 12 22 2. 40. 0.541 0.027 20036 12 23 2. 50. 0.211 0.023 20036 12 24 2. 60. 0.039 0.023 20036 12 25 2. 75. 0.150 0.023 20036 12 26 2. 90. 0.174 0.023 20036 12 27 2. 105. 0.150 0.023 20036 12 28 2. 120. 0.064 0.023 20036 12 29 2. 135. 0.076 0.023 20036 12 30 3. 30. 1.250 0.070 20036 12 31 3. 40. 0.525 0.037 20036 12 32 3. 50. 0.113 0.021 20036 12 33 3. 60. 0.107 0.021 20036 12 34 3. 75. 0.143 0.021 20036 12 35 3. 90. 0.171 0.021 20036 12 36 3. 105. 0.065 0.021 20036 12 37 3. 120. 0.041 0.021 20036 12 38 3. 135. 0.017 0.017 20036 12 39 4. 30. 1.360 0.080 20036 12 40 4. 40. 0.418 0.030 20036 12 41 4. 50. 0.100 0.020 20036 12 42 4. 60. 0.057 0.020 20036 12 43 4. 75. 0.129 0.020 20036 12 44 4. 90. 0.091 0.020 20036 12 45 4. 105. 0.050 0.020 20036 12 46 4. 120. 0.018 0.020 20036 12 47 4. 135. 0.056 0.020 20036 12 48 ENDDATA 29 0 20036 12 49 ENDSUBENT 48 0 20036 1299999 NOSUBENT 20036013 20190117 227420036 13 1 NOSUBENT 20036014 20190117 227420036 14 1 SUBENT 20036015 20190117 227420036 15 1 BIB 7 12 20036 15 2 REACTION (94-PU-239(N,INL)94-PU-239,,SIG) 20036 15 3 estimated. 20036 15 4 SAMPLE 93.63% Pu-239, 5.86% Pu-240, 0.51% Pu-241, 20036 15 5 stabilized with 1.2% gallium. 20036 15 6 ANALYSIS The assumption that the shape of the (n,n') cross- 20036 15 7 section is given by n(E) = B * exp(-E/t) was used. 20036 15 8 CORRECTION For, multiple scattering in the samples by an 20036 15 9 extension of the method by Cranberg (see REL-REF). 20036 15 10 REL-REF (M,,L.Cranberg,R,LA-2177,1959) 20036 15 11 STATUS (TABLE) Data from table 5 of AWRE-O-55/69. 20036 15 12 HISTORY (19810121A) 20036 15 13 (20190117U) SD: REL-REF added. STATUS updated. 20036 15 14 ENDBIB 12 0 20036 15 15 NOCOMMON 0 0 20036 15 16 DATA 3 3 20036 15 17 EN DATA DATA-ERR 20036 15 18 MEV B B 20036 15 19 2. 1.47 0.49 20036 15 20 3. 1.58 0.61 20036 15 21 4. 1.81 0.69 20036 15 22 ENDDATA 5 0 20036 15 23 ENDSUBENT 22 0 20036 1599999 SUBENT 20036016 20230129 231320036 16 1 BIB 6 15 20036 16 2 REACTION (94-PU-239(N,INL)94-PU-239,,DE) 20036 16 3 SAMPLE 93.63% Pu-239, 5.86% Pu-240, 0.51% Pu-241, 20036 16 4 stabilized with 1.2% gallium. 20036 16 5 ANALYSIS Inelastic neutron spectra were obtained by subtraction20036 16 6 of the fission spectra from the non-elastic spectra. 20036 16 7 The fission spectra are represented by 20036 16 8 (a * square root (E) * exp(-B * E)). 20036 16 9 REL-REF (M,,J.Terrell,J,PR,113,527,1959) 20036 16 10 STATUS (TABLE) data from table 4 of AWRE-O-55/69. 20036 16 11 (DEP,20036019) Dependent of non-elastic data, 20036 16 12 see ANALYSIS 20036 16 13 HISTORY (19810121A) 20036 16 14 (20190117A) SD: Data from Subents 017, 018 added. 20036 16 15 STATUS updated. 20036 16 16 (20230129A) SD: E-EXC-MIN/MAX -> E-MIN/MAX. 20036 16 17 ENDBIB 15 0 20036 16 18 COMMON 1 3 20036 16 19 DATA-ERR 20036 16 20 PER-CENT 20036 16 21 5. 20036 16 22 ENDCOMMON 3 0 20036 16 23 DATA 4 40 20036 16 24 EN E-MAX E-MIN DATA 20036 16 25 MEV MEV MEV B/MEV 20036 16 26 2. 0.473 0.386 0.39 20036 16 27 2. 0.566 0.473 1.39 20036 16 28 2. 0.687 0.566 1.58 20036 16 29 2. 0.807 0.687 1.14 20036 16 30 2. 0.904 0.807 1.10 20036 16 31 2. 1.022 0.904 1.02 20036 16 32 2. 1.162 1.022 0.75 20036 16 33 2. 1.243 1.162 0.45 20036 16 34 2. 1.333 1.243 0.59 20036 16 35 3. 0.506 0.409 0.62 20036 16 36 3. 0.604 0.506 1.34 20036 16 37 3. 0.704 0.604 1.40 20036 16 38 3. 0.827 0.704 1.16 20036 16 39 3. 0.929 0.827 1.14 20036 16 40 3. 1.051 0.929 0.90 20036 16 41 3. 1.197 1.051 0.53 20036 16 42 3. 1.283 1.197 0.41 20036 16 43 3. 1.378 1.283 0.37 20036 16 44 3. 1.483 1.378 0.27 20036 16 45 3. 1.602 1.483 0.26 20036 16 46 3. 1.735 1.602 0.22 20036 16 47 3. 1.886 1.735 0.22 20036 16 48 3. 2.056 1.886 0.18 20036 16 49 4. 0.554 0.445 1.55 20036 16 50 4. 0.639 0.554 1.53 20036 16 51 4. 0.746 0.639 1.65 20036 16 52 4. 0.832 0.746 1.42 20036 16 53 4. 0.935 0.832 1.16 20036 16 54 4. 1.057 0.935 0.90 20036 16 55 4. 1.128 1.057 0.57 20036 16 56 4. 1.206 1.128 0.51 20036 16 57 4. 1.292 1.206 0.35 20036 16 58 4. 1.388 1.292 0.37 20036 16 59 4. 1.495 1.388 0.21 20036 16 60 4. 1.610 1.495 0.19 20036 16 61 4. 1.750 1.610 0.11 20036 16 62 4. 1.902 1.750 0.14 20036 16 63 4. 2.070 1.902 0.14 20036 16 64 4. 2.273 2.070 0.09 20036 16 65 4. 2.500 2.273 0.10 20036 16 66 ENDDATA 42 0 20036 16 67 ENDSUBENT 66 0 20036 1699999 NOSUBENT 20036017 20190117 227420036 17 1 NOSUBENT 20036018 20190117 227420036 18 1 SUBENT 20036019 20230129 231320036 19 1 BIB 4 9 20036 19 2 REACTION (94-PU-239(N,X)0-NN-1,EM,DE) 20036 19 3 SAMPLE 93.63% Pu-239, 5.86% Pu-240, 0.51% Pu-241, 20036 19 4 stabilized with 1.2% gallium. 20036 19 5 STATUS (TABLE) Data from table 4 of AWRE-O-55/69. 20036 19 6 HISTORY (19810121A) 20036 19 7 (20190117A) SD: SF3=NON -> X; SF4=NN-1 andSF5=EM added 20036 19 8 to REACTION code. Data from Subents 020, 021 added. 20036 19 9 STATUS updated. 20036 19 10 (20230129A) SD: E-EXC-MIN/MAX -> E-MIN/MAX. 20036 19 11 ENDBIB 9 0 20036 19 12 COMMON 1 3 20036 19 13 DATA-ERR 20036 19 14 PER-CENT 20036 19 15 5. 20036 19 16 ENDCOMMON 3 0 20036 19 17 DATA 4 60 20036 19 18 EN E-MAX E-MIN DATA 20036 19 19 MEV MEV MEV B/MEV 20036 19 20 2. 0.473 0.386 2.55 20036 19 21 2. 0.566 0.473 3.47 20036 19 22 2. 0.687 0.566 3.68 20036 19 23 2. 0.807 0.687 3.23 20036 19 24 2. 0.904 0.807 3.18 20036 19 25 2. 1.022 0.904 3.07 20036 19 26 2. 1.162 1.022 2.77 20036 19 27 2. 1.243 1.162 2.38 20036 19 28 2. 1.333 1.243 2.42 20036 19 29 2. 1.429 1.333 2.46 20036 19 30 2. 2.331 1.429 1.51 20036 19 31 2. 2.587 2.331 1.31 20036 19 32 2. 2.866 2.587 1.13 20036 19 33 2. 3.190 2.866 0.97 20036 19 34 2. 3.574 3.190 0.80 20036 19 35 2. 4.033 3.574 0.62 20036 19 36 2. 4.584 4.033 0.44 20036 19 37 2. 5.257 4.584 0.29 20036 19 38 2. 6.092 5.257 0.17 20036 19 39 3. 0.506 0.409 2.70 20036 19 40 3. 0.604 0.506 3.47 20036 19 41 3. 0.704 0.604 3.58 20036 19 42 3. 0.827 0.704 3.23 20036 19 43 3. 0.929 0.827 3.18 20036 19 44 3. 1.051 0.929 2.97 20036 19 45 3. 1.197 1.051 2.53 20036 19 46 3. 1.283 1.197 2.30 20036 19 47 3. 1.378 1.283 2.23 20036 19 48 3. 1.483 1.378 2.07 20036 19 49 3. 1.602 1.483 1.98 20036 19 50 3. 1.735 1.602 1.86 20036 19 51 3. 1.886 1.735 1.76 20036 19 52 3. 2.056 1.886 1.62 20036 19 53 3. 2.251 2.056 1.57 20036 19 54 3. 2.460 2.251 1.25 20036 19 55 3. 3.727 2.460 0.85 20036 19 56 3. 4.267 3.727 0.53 20036 19 57 3. 4.871 4.267 0.34 20036 19 58 3. 5.611 4.871 0.20 20036 19 59 3. 6.534 5.611 0.11 20036 19 60 4. 0.554 0.445 3.80 20036 19 61 4. 0.639 0.554 3.72 20036 19 62 4. 0.746 0.639 3.85 20036 19 63 4. 0.832 0.746 3.42 20036 19 64 4. 0.935 0.832 3.36 20036 19 65 4. 1.057 0.935 3.06 20036 19 66 4. 1.128 1.057 2.69 20036 19 67 4. 1.206 1.128 2.57 20036 19 68 4. 1.292 1.206 2.35 20036 19 69 4. 1.388 1.292 2.30 20036 19 70 4. 1.495 1.388 2.06 20036 19 71 4. 1.610 1.495 1.98 20036 19 72 4. 1.750 1.610 1.83 20036 19 73 4. 1.902 1.750 1.74 20036 19 74 4. 2.070 1.902 1.61 20036 19 75 4. 2.273 2.070 1.46 20036 19 76 4. 2.500 2.273 1.35 20036 19 77 4. 2.744 2.500 1.36 20036 19 78 4. 5.208 2.744 0.53 20036 19 79 4. 6.144 5.208 0.13 20036 19 80 ENDDATA 62 0 20036 19 81 ENDSUBENT 80 0 20036 1999999 NOSUBENT 20036020 20190117 227420036 20 1 NOSUBENT 20036021 20190117 227420036 21 1 ENDENTRY 21 0 2003699999999