ENTRY 40507 20240617 4050700000001 SUBENT 40507001 20240617 20250110 4050700100001 BIB 9 19 4050700100002 TITLE Measurement of the 237Np/239Pu and 241Am/239Pu fission 4050700100003 cross section ratios for 0.13-7.0 MeV neutrons 4050700100004 AUTHOR (V.M.Kupriyanov, B.I.Fursov, V.I.Ivanov, G.N.Smirenkin)4050700100005 REFERENCE (J,SJA,45,1176,1978) Engl.trans.of J,AE,45,440,1978 4050700100006 (J,AE,45,440,1978) Issue 6 4050700100007 INSTITUTE (4RUSFEI) 4050700100008 REL-REF (I,40824001,B.I.Fursov+,J,AE,43,261,1977) 4050700100009 Experimental details 4050700100010 FACILITY (VDG,4RUSFEI) Electrostatic accelerators 4050700100011 INC-SOURCE (P-T,D-D,P-LI7) 4050700100012 SAMPLE Layers of 239Pu, 237Np and 241Am oxides 4050700100013 (0.2-0.4 mg/cm2, isotopic purity is ~100%) 4050700100014 HISTORY (19800609C) 4050700100015 (20180303A) M.M. Upper -> lower case correction. 4050700100016 Dates were corrected for 4-digits year. 4050700100017 Ref. SJA,45,1176,1978 was added 4050700100018 ERR-ANALYS, STATUS, decay-data were added. 4050700100019 (20240325A) VT. Revision in 002-005. 4050700100020 (20240617U) M.M. Minor correction of free text. 4050700100021 ENDBIB 19 0 4050700100022 NOCOMMON 0 0 4050700100023 ENDSUBENT 22 0 4050700199999 SUBENT 40507002 20240617 20250110 4050700200001 BIB 7 26 4050700200002 REACTION ((93-NP-237(N,F),,SIG)/(94-PU-239(N,F),,SIG)) 4050700200003 DECAY-DATA (93-NP-237,2.14E+06YR) (2.14+/-0.1 )*10**6 yr 4050700200004 (94-PU-239,2.41E+04YR) (2.41+/-0.01)*10**4 yr 4050700200005 DETECTOR (GLASD) 4050700200006 CORRECTION Corrections at 3 MeV: 4050700200007 . Angular anisotropy of fission (0.5%)4050700200008 . Fission of minority isotopes (0.2%)4050700200009 . Neutron background in laboratory (<0.2%)4050700200010 . Neutrons scattered from target structure (0.6%)4050700200011 . Neutrons from accompanying (p,n) reactions (0.8%)4050700200012 ERR-ANALYS (ERR-T) Root-mean-square sum of all uncertainties. 4050700200013 At 3 MeV: 4050700200014 . Scanning of glass detectors (0.5%)4050700200015 . Statistical error (0.9%)4050700200016 . Angular anisotropy of fission (0.3%)4050700200017 . Fission of minority isotopes (0.1%)4050700200018 . Difference of neutron fluxes through layer (0.2%)4050700200019 . Inelastic scattering of neutrons (0.4%)4050700200020 . Neutron background in laboratory (0.2%)4050700200021 . Neutrons scattered from target structure (0.3%)4050700200022 . Neutrons from accompanying (p,n) reactions (0.2%)4050700200023 (ERR-1) Ratio of numbers fissionable nuclei (0.9%)4050700200024 taking into account HL uncertainties. 4050700200025 STATUS (TABLE,,V.M.Kupriyanov+,J,SJA,45,1176,1978) Table 1 4050700200026 HISTORY (20240325A) VT. CORRECTION, ERR-ANALYS and STATUS 4050700200027 updated. 4050700200028 ENDBIB 26 0 4050700200029 COMMON 1 3 4050700200030 ERR-1 4050700200031 PER-CENT 4050700200032 0.9 4050700200033 ENDCOMMON 3 0 4050700200034 DATA 4 3 4050700200035 EN EN-ERR DATA ERR-T 4050700200036 MEV KEV NO-DIM PER-CENT 4050700200037 2.0 60. 0.832 1.4 4050700200038 2.5 72. 0.860 1.5 4050700200039 3.0 78. 0.873 1.5 4050700200040 ENDDATA 5 0 4050700200041 ENDSUBENT 40 0 4050700299999 SUBENT 40507003 20240617 20250110 4050700300001 BIB 7 26 4050700300002 REACTION ((95-AM-241(N,F),,SIG)/(94-PU-239(N,F),,SIG)) 4050700300003 DECAY-DATA (95-AM-241,432.YR) 432+/-4 yr 4050700300004 (94-PU-239,2.41E+04YR) (2.41+/-0.01)*10**4 yr 4050700300005 DETECTOR (GLASD) 4050700300006 CORRECTION Corrections at 3 MeV: 4050700300007 . Angular anisotropy of fission (0.8%)4050700300008 . Fission of minority isotopes (0.2%)4050700300009 . Neutron background in laboratory (<0.2%)4050700300010 . Neutrons scattered from target structure (1.4%)4050700300011 . Neutrons from accompanying (p,n) reactions (1.2%)4050700300012 ERR-ANALYS (ERR-T) Root-mean-square sum of all uncertainties. 4050700300013 At 3 MeV: 4050700300014 . Scanning of glass detectors (0.5%)4050700300015 . Statistical error (1.4%)4050700300016 . Angular anisotropy of fission (0.3%)4050700300017 . Fission of minority isotopes (0.1%)4050700300018 . Difference of neutron fluxes through layer (0.2%)4050700300019 . Inelastic scattering of neutrons (0.4%)4050700300020 . Neutron background in laboratory (0.2%)4050700300021 . Neutrons scattered from target structure (0.3%)4050700300022 . Neutrons from accompanying (p,n) reactions (0.3%)4050700300023 (ERR-1) Ratio of numbers fissionable nuclei (1.3%)4050700300024 taking into account HL uncertainties. 4050700300025 STATUS (TABLE,,V.M.Kupriyanov+,J,SJA,45,1176,1978) Table 1 4050700300026 HISTORY (20240325A) VT. CORRECTION, ERR-ANALYS and STATUS 4050700300027 updated. 4050700300028 ENDBIB 26 0 4050700300029 COMMON 1 3 4050700300030 ERR-1 4050700300031 PER-CENT 4050700300032 1.3 4050700300033 ENDCOMMON 3 0 4050700300034 DATA 4 3 4050700300035 EN EN-ERR DATA ERR-T 4050700300036 MEV KEV NO-DIM PER-CENT 4050700300037 2.0 60. 0.935 2.0 4050700300038 2.5 72. 0.970 2.0 4050700300039 3.0 78. 0.997 2.1 4050700300040 ENDDATA 5 0 4050700300041 ENDSUBENT 40 0 4050700399999 SUBENT 40507004 20240617 20250110 4050700400001 BIB 7 17 4050700400002 REACTION ((93-NP-237(N,F),,SIG)/(94-PU-239(N,F),,SIG)) 4050700400003 DETECTOR (IOCH) 4050700400004 ANALYSIS Normalized to the glass detector dataset 4050700400005 CORRECTION Corrected for 4050700400006 . neutron scattered from target structure 4050700400007 (12% at 0.13 MeV, 2.2% at 1.5-7.0 MeV) 4050700400008 . (d,n) neutrons (0.2-8.1% at 3.6-7.0 MeV) 4050700400009 . (p,n) neutrons (1.2% at < 3 MeV) 4050700400010 . background in the laboratory (<0.4%) 4050700400011 ERR-ANALYS (ERR-T) Root-mean-square sum of all uncertainties from 4050700400012 - Energy dependence of the shape ratio 4050700400013 (ERR-1) Absolute ratios for normalization (1.5%)4050700400014 (ERR-2) Normalization procedure of shape (0.25%)4050700400015 STATUS (TABLE,,V.M.Kupriyanov+,J,SJA,45,1176,1978) Table 3 4050700400016 (DEP,40507002) Glass detector dataset 4050700400017 HISTORY (20240325A) VT. CORRECTION, ERR-ANALYS and STATUS 4050700400018 updated. 4050700400019 ENDBIB 17 0 4050700400020 COMMON 2 3 4050700400021 ERR-1 ERR-2 4050700400022 PER-CENT PER-CENT 4050700400023 1.5 0.25 4050700400024 ENDCOMMON 3 0 4050700400025 DATA 4 61 4050700400026 EN EN-ERR DATA ERR-T 4050700400027 MEV KEV NO-DIM PER-CENT 4050700400028 0.130 21. 0.015 4.8 4050700400029 0.180 20. 0.022 4.3 4050700400030 0.230 19. 0.025 4.1 4050700400031 0.280 18. 0.034 4.0 4050700400032 0.350 38. 0.068 3.5 4050700400033 0.400 37. 0.107 2.9 4050700400034 0.450 36. 0.174 2.7 4050700400035 0.500 34. 0.265 2.6 4050700400036 0.550 33. 0.356 2.4 4050700400037 0.600 32. 0.441 2.3 4050700400038 0.650 32. 0.539 2.6 4050700400039 0.700 32. 0.613 2.3 4050700400040 0.750 32. 0.650 2.3 4050700400041 0.800 31. 0.686 2.3 4050700400042 0.850 31. 0.731 2.1 4050700400043 0.900 31. 0.763 2.1 4050700400044 0.950 31. 0.781 2.0 4050700400045 1.00 31. 0.810 1.9 4050700400046 1.05 34. 0.814 1.9 4050700400047 1.10 37. 0.812 1.9 4050700400048 1.15 40. 0.812 1.9 4050700400049 1.20 42. 0.811 1.9 4050700400050 1.25 44. 0.807 1.9 4050700400051 1.30 45. 0.804 1.8 4050700400052 1.35 46. 0.805 1.8 4050700400053 1.40 47. 0.809 1.7 4050700400054 1.45 48. 0.811 1.7 4050700400055 1.50 49. 0.814 1.7 4050700400056 1.60 58. 0.820 1.7 4050700400057 1.70 59. 0.828 1.7 4050700400058 1.80 61. 0.835 1.7 4050700400059 1.90 64. 0.830 1.7 4050700400060 2.00 66. 0.836 1.8 4050700400061 2.10 68. 0.841 1.7 4050700400062 2.20 69. 0.841 1.8 4050700400063 2.30 70. 0.844 1.8 4050700400064 2.40 71. 0.854 1.8 4050700400065 2.50 73. 0.862 1.7 4050700400066 2.60 75. 0.861 1.7 4050700400067 2.70 77. 0.863 1.7 4050700400068 2.80 78. 0.868 1.7 4050700400069 2.90 80. 0.868 1.7 4050700400070 3.00 82. 0.866 1.7 4050700400071 3.60 190. 0.858 1.8 4050700400072 3.80 180. 0.864 1.8 4050700400073 4.00 145. 0.859 1.8 4050700400074 4.20 140. 0.865 1.8 4050700400075 4.40 130. 0.861 1.7 4050700400076 4.60 128. 0.861 1.7 4050700400077 4.80 124. 0.860 1.7 4050700400078 5.00 125. 0.854 1.7 4050700400079 5.20 128. 0.859 1.7 4050700400080 5.40 130. 0.852 1.8 4050700400081 5.60 133. 0.857 1.9 4050700400082 5.80 136. 0.874 1.9 4050700400083 6.00 140. 0.905 2.0 4050700400084 6.20 144. 0.939 2.2 4050700400085 6.40 150. 0.974 2.2 4050700400086 6.60 157. 0.986 2.5 4050700400087 6.80 165. 0.993 2.3 4050700400088 7.00 172. 0.983 2.5 4050700400089 ENDDATA 63 0 4050700400090 ENDSUBENT 89 0 4050700499999 SUBENT 40507005 20240617 20250110 4050700500001 BIB 7 17 4050700500002 REACTION ((95-AM-241(N,F),,SIG)/(94-PU-239(N,F),,SIG)) 4050700500003 DETECTOR (IOCH) 4050700500004 ANALYSIS Normalized to the glass detector dataset 4050700500005 CORRECTION Corrected for 4050700500006 . neutron scattered from target structure 4050700500007 (12% at 0.13 MeV, 2.2% at 1.5-7.0 MeV) 4050700500008 . (d,n) neutrons (0.2-8.1% at 3.6-7.0 MeV) 4050700500009 . (p,n) neutrons (1.2% at < 3 MeV) 4050700500010 . background in the laboratory (<0.4%) 4050700500011 ERR-ANALYS (ERR-T) Root-mean-square sum of all uncertainties from 4050700500012 - Energy dependence of the shape ratio 4050700500013 (ERR-1) Absolute ratios for normalization (2%)4050700500014 (ERR-2) Normalization procedure of shape (0.25%)4050700500015 STATUS (TABLE,,V.M.Kupriyanov+,J,SJA,45,1176,1978) Table 3 4050700500016 (DEP,40507003) Glass detector dataset 4050700500017 HISTORY (20240325A) VT. CORRECTION, ERR-ANALYS and STATUS 4050700500018 updated. 4050700500019 ENDBIB 17 0 4050700500020 COMMON 2 3 4050700500021 ERR-1 ERR-2 4050700500022 PER-CENT PER-CENT 4050700500023 2. 0.25 4050700500024 ENDCOMMON 3 0 4050700500025 DATA 4 61 4050700500026 EN EN-ERR DATA ERR-T 4050700500027 MEV KEV NO-DIM PER-CENT 4050700500028 0.130 21. 0.012 4.3 4050700500029 0.180 20. 0.016 4.4 4050700500030 0.230 19. 0.019 4.2 4050700500031 0.280 18. 0.024 4.5 4050700500032 0.350 38. 0.030 3.6 4050700500033 0.400 37. 0.037 3.2 4050700500034 0.450 36. 0.050 3.3 4050700500035 0.500 34. 0.064 3.1 4050700500036 0.550 33. 0.091 3.3 4050700500037 0.600 32. 0.112 3.3 4050700500038 0.650 32. 0.171 3.2 4050700500039 0.700 32. 0.232 3.3 4050700500040 0.750 32. 0.314 3.4 4050700500041 0.800 31. 0.388 3.2 4050700500042 0.850 31. 0.494 3.1 4050700500043 0.900 31. 0.565 3.2 4050700500044 0.950 31. 0.658 3.1 4050700500045 1.00 31. 0.734 2.7 4050700500046 1.05 34. 0.786 2.8 4050700500047 1.10 37. 0.807 2.7 4050700500048 1.15 40. 0.857 2.8 4050700500049 1.20 42. 0.876 2.6 4050700500050 1.25 44. 0.902 2.6 4050700500051 1.30 45. 0.907 2.6 4050700500052 1.35 46. 0.911 2.6 4050700500053 1.40 47. 0.921 2.6 4050700500054 1.45 48. 0.924 2.5 4050700500055 1.50 49. 0.928 2.3 4050700500056 1.60 58. 0.924 2.4 4050700500057 1.70 59. 0.928 2.3 4050700500058 1.80 61. 0.931 2.4 4050700500059 1.90 64. 0.936 2.3 4050700500060 2.00 66. 0.937 2.2 4050700500061 2.10 68. 0.948 2.3 4050700500062 2.20 69. 0.946 2.2 4050700500063 2.30 70. 0.956 2.2 4050700500064 2.40 71. 0.960 2.2 4050700500065 2.50 73. 0.970 2.2 4050700500066 2.60 75. 0.971 2.3 4050700500067 2.70 77. 0.977 2.2 4050700500068 2.80 78. 0.984 2.2 4050700500069 2.90 80. 0.984 2.2 4050700500070 3.00 82. 0.994 2.2 4050700500071 3.60 190. 1.027 2.4 4050700500072 3.80 180. 1.027 2.4 4050700500073 4.00 145. 1.038 2.4 4050700500074 4.20 140. 1.049 2.4 4050700500075 4.40 130. 1.055 2.4 4050700500076 4.60 128. 1.061 2.3 4050700500077 4.80 124. 1.066 2.4 4050700500078 5.00 125. 1.062 2.3 4050700500079 5.20 128. 1.066 2.3 4050700500080 5.40 130. 1.072 2.3 4050700500081 5.60 133. 1.077 2.5 4050700500082 5.80 136. 1.072 2.5 4050700500083 6.00 140. 1.059 2.6 4050700500084 6.20 144. 1.051 2.8 4050700500085 6.40 150. 1.070 2.7 4050700500086 6.60 157. 1.081 2.7 4050700500087 6.80 165. 1.056 2.7 4050700500088 7.00 172. 1.064 2.9 4050700500089 ENDDATA 63 0 4050700500090 ENDSUBENT 89 0 4050700599999 ENDENTRY 5 0 4050799999999