ENTRY 40824 20220118 42044082400000001 SUBENT 40824001 20220118 42044082400100001 BIB 9 30 4082400100002 TITLE Measurement of the ratio of the 239Pu and 235U fission 4082400100003 cross sections for 0.024-7.4-MeV neutrons 4082400100004 AUTHOR (B.I.Fursov, V.M.Kupriyanov, V.I.Ivanov, G.N.Smirenkin)4082400100005 REFERENCE (J,AE,43,261,1977) 4082400100006 (J,SJA,43,894,1977) 4082400100007 #doi:10.1007/BF01117993 4082400100008 (R,YFI-25,3,1977) Reprint of J,AE,43,261,1977. 4082400100009 In INDC(CCP)-171 - only first author and title. 4082400100010 ((C,75KIEV,6,3,1975)= 4082400100011 (R,INDC(CCP)-099,(6),3,1975)) Prelim. data in tables 4082400100012 INSTITUTE (4RUSFEI) 4082400100013 FACILITY (VDG) 4082400100014 INC-SOURCE (P-LI7) En=127 keV to 320 keV 4082400100015 (P-T) 4082400100016 (D-D) En=3.6 MeV to 7.4 MeV 4082400100017 SAMPLE Uranium and plutonium oxides (10 and 15 mm diam.) 4082400100018 deposited on Al backing (0.06 mm thick). 4082400100019 STATUS (APRVD) Smirenkin 1984-10 4082400100020 . This ENTRY 40824 supersedes ENTRY 40501. 4082400100021 HISTORY (19850125C) 4082400100022 (20070914A) Common block Sub.002 was corrected. 4082400100023 Dates were corrected for 4-digits year. 4082400100024 Errors were added in Sub.003. M.M. 4082400100025 (20101220U) Misprint was corrected. 4082400100026 ERR-5 -> ERR-S was corrected in Subent 002. 4082400100027 (20170724A) On. ASSUMED deleted. Major rev. in 002-003.4082400100028 (20210512U) On. Minor revision in 003. 4082400100029 (20220118U) M.M. Misprint in YFI ref. was corrected. 4082400100030 Ref. of INDC(CCP)-099 was added. 4082400100031 Minor correction of free text. 4082400100032 ENDBIB 30 0 4082400100033 NOCOMMON 0 0 4082400100034 ENDSUBENT 33 0 4082400199999 SUBENT 40824002 20220118 42044082400200001 BIB 10 43 4082400200002 REACTION ((94-PU-239(N,F),,SIG)/(92-U-235(N,F),,SIG)) 4082400200003 SAMPLE Mass quantification ( ratio of number of fissile nuclei4082400200004 in layers, 239Pu/235U) was attempted by thermal fission4082400200005 cross section measurement (1.3848 at 24.7 deg-C 4082400200006 assumed) and alpha spectroscopy. 4082400200007 . 239Pu contents are 4082400200008 239Pu 99.891%, 240Pu 0.109 % 4082400200009 . 235U contents are 4082400200010 235U 91.2326%, 234U 1.1003+/-0.0073%, 4082400200011 236U 0.0036%, 238U 7.6635% 4082400200012 DECAY-DATA (92-U-235,7.0381E+08YR) 7.0381+/-0.0048E+08 year 4082400200013 DETECTOR (GLASD) 4082400200014 MONITOR Absolute measurement 4082400200015 CORRECTION Corrected for 4082400200016 - neutron flux difference between 239Pu and 235U 4082400200017 layers (1.22% at 3 MeV)4082400200018 - fission angular anisotropy (0.72% at 3 MeV)4082400200019 - admixture isotopes fission (4.96% at 3 MeV)4082400200020 - sample-scattered neutron background (0.30% at 3 MeV)4082400200021 - experimental-hall-scattered neutrons(0.12% at 3 MeV)4082400200022 - (p,n) neutron background (0.22% at 3 MeV)4082400200023 ERR-ANALYS (ERR-T) Total uncertainty (1.14% at 3 MeV) includes: 4082400200024 - glass detector scanning (0.40% at 3 MeV)4082400200025 - neutron flux difference between 239Pu and 235U 4082400200026 layers (0.18% at 3 MeV)4082400200027 - fission angular anisotropy (0.35% at 3 MeV)4082400200028 - statistics of measurement with fast neutrons 4082400200029 (0.47% at 3 MeV)4082400200030 - admixture isotopes fission (0.17% at 3 MeV)4082400200031 - sample-scattered neutron background (0.16% at 3 MeV)4082400200032 - experimental-hall-scattered neutrons(0.10% at 3 MeV)4082400200033 - (p,n) neutron background (0.10% at 3 MeV)4082400200034 - inelastic scattering (0.20% at 3 MeV)4082400200035 and ERR-1. 4082400200036 (ERR-1) 239Pu/235U ratio of number of fissile nuclei in4082400200037 layers (0.81%) 4082400200038 FLAG (1.) Partial uncertainties given under ERR-ANALYS. 4082400200039 STATUS (TABLE) Table 1 of Sov.J.Atom.Energy 43(1977)894 -DATA,4082400200040 Table 2 - uncertainties. 4082400200041 (COREL,40824003) Data from ionization chamber 4082400200042 HISTORY (20170724A) On. Coded uncertainties moved to free text.4082400200043 Numerical data checked against the article table. 4082400200044 (20220118U) M.M. ERR-HL was added in COMMON block. 4082400200045 ENDBIB 43 0 4082400200046 COMMON 2 3 4082400200047 ERR-1 ERR-HL 4082400200048 PER-CENT YR 4082400200049 0.81 0.0048E+08 4082400200050 ENDCOMMON 3 0 4082400200051 DATA 5 13 4082400200052 EN EN-RSL DATA ERR-T FLAG 4082400200053 MEV KEV NO-DIM PER-CENT NO-DIM 4082400200054 0.127 20. 0.995 1.53 4082400200055 0.320 40. 1.200 1.30 4082400200056 0.500 34. 1.347 1.56 4082400200057 0.750 32. 1.469 1.31 4082400200058 1.00 31. 1.432 1.26 4082400200059 1.35 50. 1.537 1.30 4082400200060 1.70 60. 1.547 1.22 4082400200061 2.25 72. 1.559 1.12 4082400200062 3.00 84. 1.554 1.14 1. 4082400200063 4.00 146. 1.580 1.30 4082400200064 5.00 120. 1.611 1.36 4082400200065 6.00 142. 1.642 1.16 4082400200066 7.00 173. 1.423 1.32 4082400200067 ENDDATA 15 0 4082400200068 ENDSUBENT 67 0 4082400299999 SUBENT 40824003 20220118 42044082400300001 BIB 8 34 4082400300002 REACTION ((94-PU-239(N,F),,SIG)/(92-U-235(N,F),,SIG)) 4082400300003 ANALYSIS Normalized to the glass detector data set 4082400300004 SAMPLE . 239Pu contents are 4082400300005 239Pu 99.891%, 240Pu 0.109 % 4082400300006 . 235U contents are 4082400300007 235U 99.9955%, 234U 0.0010% 4082400300008 236U 0.0035%, 238U <0.0005% 4082400300009 DETECTOR (IOCH) Double ionization chamber with two pairs of 4082400300010 239Pu and 235U layers 4082400300011 CORRECTION Corrected for 4082400300012 - admixture isotopes fission (<0.15%) 4082400300013 - (d,n) neutron background (3.45%) 4082400300014 - fission chamber efficiency energy dependence 4082400300015 (0.1-2.5%) 4082400300016 ERR-ANALYS (ERR-T) Total uncertainty includes: 4082400300017 (ERR-1,0.1,1.5)Energy dependence of the ratio(0.1-1.5%)4082400300018 including 4082400300019 - statistics of measurement with fast neutrons 4082400300020 - admixture isotopes fission (0.1%) 4082400300021 - sample-scattered neutron background (0.35-1.05%) 4082400300022 - experimental-hall-scattered neutrons (0.32-0.80%) 4082400300023 - (d,n) neutron background (<0.54%) 4082400300024 - inelastic scattering 4082400300025 - fission chamber efficiency energy dependence (0.3%) 4082400300026 (ERR-2) Absolute ratio(average) of glass detector(1.3%)4082400300027 (ERR-3) Normalization of energy dependent curve (0.22%)4082400300028 STATUS (TABLE) Table 3 of Sov.J.Atom.Energy 43(1977)896 -DATA,4082400300029 text page 898 - uncertainties. 4082400300030 (DEP,40824002) Absolute ratio - 4082400300031 (COREL,40824002) data from glass detector - 4082400300032 which Subent 003 data were normalized to. 4082400300033 HISTORY (20170724A) On. ERR-ANALYS updated. Numerical data 4082400300034 checked against the article table. 4082400300035 (20210512U) On. "1.14% at 3 MeV" in ERR-ANALYS deleted.4082400300036 ENDBIB 34 0 4082400300037 COMMON 2 3 4082400300038 ERR-2 ERR-3 4082400300039 PER-CENT PER-CENT 4082400300040 1.3 0.22 4082400300041 ENDCOMMON 3 0 4082400300042 DATA 4 80 4082400300043 EN EN-RSL DATA ERR-T 4082400300044 MEV KEV NO-DIM PER-CENT 4082400300045 0.024 12. 0.764 2.00 4082400300046 0.040 14. 0.829 1.92 4082400300047 0.060 17. 0.881 1.75 4082400300048 0.080 21. 0.934 1.72 4082400300049 0.100 25. 0.980 1.63 4082400300050 0.127 20. 1.005 1.46 4082400300051 0.150 20. 1.038 1.59 4082400300052 0.180 20. 1.067 1.49 4082400300053 0.210 19. 1.107 1.54 4082400300054 0.240 18. 1.134 1.47 4082400300055 0.270 18. 1.170 1.67 4082400300056 0.300 18. 1.185 1.50 4082400300057 0.320 40. 1.210 1.42 4082400300058 0.350 38. 1.225 1.48 4082400300059 0.380 37. 1.234 1.44 4082400300060 0.420 36. 1.268 1.45 4082400300061 0.460 35. 1.312 1.44 4082400300062 0.500 34. 1.351 1.44 4082400300063 0.540 33. 1.363 1.44 4082400300064 0.580 33. 1.374 1.57 4082400300065 0.620 32. 1.413 1.47 4082400300066 0.660 32. 1.436 1.50 4082400300067 0.700 32. 1.446 1.46 4082400300068 0.750 32. 1.467 1.48 4082400300069 0.780 31. 1.492 1.48 4082400300070 0.820 31. 1.506 1.52 4082400300071 0.860 31. 1.493 1.49 4082400300072 0.900 31. 1.474 1.44 4082400300073 0.950 31. 1.459 1.45 4082400300074 1.00 31. 1.443 1.46 4082400300075 1.050 34. 1.437 1.44 4082400300076 1.100 37. 1.444 1.46 4082400300077 1.150 40. 1.464 1.47 4082400300078 1.200 42. 1.494 1.41 4082400300079 1.250 44. 1.507 1.41 4082400300080 1.300 45. 1.534 1.41 4082400300081 1.350 46. 1.552 1.41 4082400300082 1.400 47. 1.563 1.42 4082400300083 1.450 48. 1.563 1.41 4082400300084 1.500 49. 1.572 1.41 4082400300085 1.6 60. 1.560 1.41 4082400300086 1.7 61. 1.555 1.43 4082400300087 1.8 63. 1.562 1.43 4082400300088 1.9 66. 1.558 1.42 4082400300089 2.0 68. 1.554 1.41 4082400300090 2.1 70. 1.558 1.40 4082400300091 2.2 71. 1.553 1.41 4082400300092 2.25 72. 1.550 1.40 4082400300093 2.3 73. 1.550 1.40 4082400300094 2.4 74. 1.548 1.40 4082400300095 2.5 75. 1.547 1.40 4082400300096 2.6 77. 1.547 1.40 4082400300097 2.7 78. 1.548 1.40 4082400300098 2.8 79. 1.547 1.40 4082400300099 2.9 82. 1.553 1.41 4082400300100 3.0 84. 1.556 1.41 4082400300101 3.1 86. 1.559 1.41 4082400300102 3.2 88. 1.559 1.41 4082400300103 3.3 91. 1.564 1.41 4082400300104 3.4 93. 1.565 1.42 4082400300105 3.6 192. 1.568 1.47 4082400300106 3.8 182. 1.571 1.44 4082400300107 4.0 146. 1.570 1.43 4082400300108 4.2 141. 1.568 1.43 4082400300109 4.4 132. 1.572 1.43 4082400300110 4.6 131. 1.577 1.43 4082400300111 4.8 125. 1.587 1.44 4082400300112 5.0 126. 1.590 1.41 4082400300113 5.2 129. 1.600 1.41 4082400300114 5.4 131. 1.600 1.42 4082400300115 5.6 135. 1.618 1.42 4082400300116 5.8 138. 1.632 1.42 4082400300117 6.0 142. 1.637 1.41 4082400300118 6.2 147. 1.614 1.42 4082400300119 6.4 152. 1.550 1.43 4082400300120 6.6 160. 1.486 1.42 4082400300121 6.8 167. 1.442 1.44 4082400300122 7.0 173. 1.402 1.44 4082400300123 7.2 178. 1.380 1.45 4082400300124 7.4 183. 1.355 1.48 4082400300125 ENDDATA 82 0 4082400300126 ENDSUBENT 125 0 4082400399999 ENDENTRY 3 0 4082499999999