ENTRY 40474 20240618 421740474000 1 SUBENT 40474001 20240618 421740474001 1 BIB 10 43 40474001 2 TITLE Measurement of the 233U and 241Pu fission cross 40474001 3 sections relative to the 235U fission cross section 40474001 4 in the neutron energy range 0.024 - 7.4 MeV 40474001 5 AUTHOR (B.I.Fursov, V.M.Kupriyanov, G.N.Smirenkii) 40474001 6 Compiler's note: "Smirenkii" in J,SJA,44,262,1978 40474001 7 should read "Smirenkin". 40474001 8 INSTITUTE (4RUSFEI) 40474001 9 REFERENCE (J,SJA,44,262,1978) Eng.trans.of AE,44,236,1978 40474001 10 (J,AE,44,236,1978) Final results 40474001 11 (P,YFI-25,10,1977) Table in primary ref. repeated. 40474001 12 INDC(CCP)-171 - table of YFI-25 content only. 40474001 13 REL-REF (I,40501001,B.I.Fursov+,C,75KIEV,6,3,1975) 40474001 14 =INDC(CCP)-099,(6),3,1975 40474001 15 Experimental details 40474001 16 FACILITY (VDG,4RUSFEI) Electrostatic accelerators 40474001 17 INC-SOURCE (P-T,D-D,P-LI7) TiH2 for T(p,n) neutrons, LiF on Mo 40474001 18 for 7Li(p,n) neutrons. Below En=127 keV 7Li(p,n) 40474001 19 neutrons at 120 deg used. 40474001 20 METHOD The result from the glass detector was normalized 40474001 21 to the thermal value, and the result from the fission 40474001 22 chamber was normalized to the glass detector result. 40474001 23 CORRECTION Corrected for 40474001 24 - background neutrons from Mo and Ti backing 40474001 25 - fission of admixture, 40474001 26 - angular anisotropy of fission (for glass method), 40474001 27 - energy dependence of fragment detection efficiency,40474001 28 HISTORY (19781222C) Compiled at the centre 40474001 29 (20150218A) SD: Updated to new date formats,lower case.40474001 30 Corrections according last EXFOR rules and Dict. 40474001 31 (20170313A) M.M. Articles were checked, BIB information40474001 32 was updated in FACILITY, INC-SOURCE,STATUS,COMMENT. 40474001 33 Subent 002 was split into Subents 002,004, 40474001 34 Subent 003 was split into Subents 003,003 40474001 35 to present partial uncertainties correctly for two 40474001 36 different methods. 40474001 37 75KIEV,6,3,1975 was moved in REL-REF. 40474001 38 (20180724A) On. Major revisions in 002-004. 40474001 39 (20201213A) On. Major revisions in 004-005. 40474001 40 (20210920U) M.M. Minor correction of free text in 40474001 41 Subents 004, 005. 40474001 42 (20240327U) On. Minor revisions in 002-003. 40474001 43 (20240618U) M.M. Minor correction of free text. 40474001 44 STATUS was updated for new rule. 40474001 45 ENDBIB 43 0 40474001 46 NOCOMMON 0 0 40474001 47 ENDSUBENT 46 0 4047400199999 SUBENT 40474002 20240618 421740474002 1 BIB 9 30 40474002 2 REACTION ((92-U-233(N,F),,SIG)/(92-U-235(N,F),,SIG)) 40474002 3 SAMPLE (92-U-233,ENR=0.9331) 40474002 4 (92-U-235,ENR=0.9997) 40474002 5 DETECTOR (GLASD) 40474002 6 MONITOR ((92-U-233(N,F),,SIG,,MXW)/(92-U-235(N,F),,SIG,,MXW)) 40474002 7 Measured by neutrons (thermal to superthermal ratio 40474002 8 ~1E+04, spectrum temperature 27+/-11 deg-C) from the 40474002 9 BR-10 reactor thermal column. 40474002 10 REL-REF (R,,C.Westcott,R,AECL-1101,1960) 40474002 11 Energy dependence of 233,235U(n,f) g-factor 40474002 12 CORRECTION Corrections factors at En=3 MeV: 40474002 13 Angular anisotropy 0.38 40474002 14 Fission of admixture isotopes 2.96 40474002 15 Neutrons scattered on target structure 0.15 40474002 16 Laboratory neutron background 0.12 40474002 17 Background of neutrons from (p,n) reactions 0.10 40474002 18 ERR-ANALYS Errors at En=3 MeV: 40474002 19 Glass detector field of view 0.40% 40474002 20 Angular anisotropy 0.35% 40474002 21 Statistics of fast neutron measurement 0.62% 40474002 22 Fission of admixture isotopes 0.16% 40474002 23 Neutrons scattered on target structure 0.32% 40474002 24 Laboratory neutron background 0.28% 40474002 25 Background of neutrons from (p,n) reactions 0.18% 40474002 26 Inelastic scattering 0.20% 40474002 27 (ERR-T) Mean square sum of all uncertainties involved 40474002 28 (ERR-1) 233U/235U atom numbers ratio (0.76%) 40474002 29 STATUS (TABLE,,B.I.Fursov+,J,SJA,44,262,1978)) Table 1 40474002 30 HISTORY (20180724A) On. MONITOR added. 40474002 31 (20240327U) On. STATUS=COREL deleted. 40474002 32 ENDBIB 30 0 40474002 33 COMMON 3 3 40474002 34 KT-NRM MONIT ERR-1 40474002 35 DEG-C NO-DIM PER-CENT 40474002 36 27. 0.9293 0.76 40474002 37 ENDCOMMON 3 0 40474002 38 DATA 4 11 40474002 39 EN EN-ERR DATA ERR-T 40474002 40 MEV KEV NO-DIM PER-CENT 40474002 41 0.127 20. 1.467 1.20 40474002 42 0.320 40. 1.681 1.16 40474002 43 0.500 34. 1.680 1.26 40474002 44 1.000 31. 1.557 1.21 40474002 45 1.50 49. 1.521 1.28 40474002 46 2.25 72. 1.501 1.20 40474002 47 3.00 84. 1.493 1.24 40474002 48 4.00 146. 1.471 1.16 40474002 49 5.00 126. 1.442 1.20 40474002 50 6.00 142. 1.497 1.27 40474002 51 7.00 173. 1.351 1.39 40474002 52 ENDDATA 13 0 40474002 53 ENDSUBENT 52 0 4047400299999 SUBENT 40474003 20240618 421740474003 1 BIB 10 33 40474003 2 REACTION ((94-PU-241(N,F),,SIG)/(92-U-235(N,F),,SIG)) 40474003 3 SAMPLE (94-PU-241,ENR=0.9602) 40474003 4 (92-U-235,ENR=0.9997) 40474003 5 DETECTOR (GLASD) 40474003 6 MONITOR ((94-PU-241(N,F),,SIG,,MXW)/(92-U-235(N,F),,SIG,,MXW)) 40474003 7 Measured by neutrons (thermal to superthermal ratio 40474003 8 ~1E+04, spectrum temperature 27+/-11 deg-C) from the 40474003 9 BR-10 reactor thermal column. 40474003 10 MONIT-REF (,H.Lemmel,C,75WASH,1,286,1975) 40474003 11 REL-REF (R,,C.Westcott,R,AECL-1101,1960) 40474003 12 Energy dependence of 235U(n,f) g-factor 40474003 13 (R,,C.Wagemans+,J,ANE,2,541,1975) 40474003 14 Energy dependence of 241Pu(n,f) g-factor 40474003 15 CORRECTION Corrections factors at En=3 MeV: 40474003 16 Angular anisotropy 0.52 40474003 17 Fission of admixture isotopes 5.03 40474003 18 Neutrons scattered on target structure 0.47 40474003 19 Laboratory neutron background 0.14 40474003 20 Background of neutrons from (p,n) reactions 0.16 40474003 21 ERR-ANALYS Errors at En=3 MeV: 40474003 22 Glass detector field of view 0.40% 40474003 23 Angular anisotropy 0.30% 40474003 24 Statistics of fast neutron measurement 0.58% 40474003 25 Fission of admixture isotopes 0.28% 40474003 26 Background of neutrons scattered on target 0.30% 40474003 27 Laboratory neutron background 0.24% 40474003 28 Background of neutrons from (p,n) reactions 0.22% 40474003 29 Inelastic scattering 0.20% 40474003 30 (ERR-T) Mean square sum of all uncertainties involved 40474003 31 (ERR-1) 233U/235U atom numbers ratio (1.35%) 40474003 32 STATUS (TABLE,,B.I.Fursov+,J,SJA,44,262,1978)) Table 1 40474003 33 HISTORY (20180724A) On. MONITOR added. 40474003 34 (20240327U) On. STATUS=COREL deleted. 40474003 35 ENDBIB 33 0 40474003 36 COMMON 3 3 40474003 37 KT-NRM MONIT ERR-1 40474003 38 DEG-C NO-DIM PER-CENT 40474003 39 27. 1.8692 1.35 40474003 40 ENDCOMMON 3 0 40474003 41 DATA 4 11 40474003 42 EN EN-ERR DATA ERR-T 40474003 43 MEV KEV NO-DIM PER-CENT 40474003 44 0.127 20. 1.344 1.66 40474003 45 0.320 40. 1.344 1.64 40474003 46 0.500 34. 1.310 1.61 40474003 47 1.000 31. 1.304 1.70 40474003 48 1.50 49. 1.401 1.73 40474003 49 2.25 72. 1.302 1.64 40474003 50 3.00 84. 1.293 1.65 40474003 51 4.00 146. 1.296 1.75 40474003 52 5.00 126. 1.301 1.67 40474003 53 6.00 142. 1.345 1.69 40474003 54 7.00 173. 1.238 1.74 40474003 55 ENDDATA 13 0 40474003 56 ENDSUBENT 55 0 4047400399999 SUBENT 40474004 20240618 421740474004 1 BIB 7 25 40474004 2 REACTION ((92-U-233(N,F),,SIG)/(92-U-235(N,F),,SIG)) 40474004 3 SAMPLE (92-U-233,ENR=0.9331) 40474004 4 (92-U-235,ENR=0.9997) 40474004 5 DETECTOR (IOCH) 40474004 6 MONITOR ((92-U-233(N,F),,SIG)/(92-U-235(N,F),,SIG)) 40474004 7 Normalized to the glass detector result 40474004 8 ERR-ANALYS -Statistical error from scattering of results 40474004 9 (0.2-1.3% at 0 deg, increasing to 1.3% at 24 keV) 40474004 10 -Scattering and laboratory neutron background 40474004 11 (1.1% at 120 deg) 40474004 12 -(d,n) neutron background (<0.8%) 40474004 13 -Basic data 40474004 14 (1.4%,increasing to 2.2-2.4% at the energy rage limit)40474004 15 (ERR-T) Quadrature sum of the following errors: 40474004 16 (ERR-2,0.5,1.8) Energy dependence of fission cross 40474004 17 section ratio (0.5-1.8%)40474004 18 (ERR-3) Absolute values obtained by the glass method 40474004 19 (1.23%)40474004 20 (ERR-4) Normalization of the energy curve to the 40474004 21 reference values (0.16%)40474004 22 STATUS (TABLE,,B.I.Fursov+,J,SJA,44,262,1978)) Table 2 40474004 23 (DEP,40474002) Glass detector result 40474004 24 HISTORY (20170313A) M.M. Data were moved from Subent 002. 40474004 25 (20180724A) On. DATA corrected at 0.024 and 2.30 MeV. 40474004 26 (20201213A) On. ANALYSIS -> MONITOR.ERR-ANALYS revised.40474004 27 ENDBIB 25 0 40474004 28 COMMON 2 3 40474004 29 ERR-3 ERR-4 40474004 30 PER-CENT PER-CENT 40474004 31 1.23 0.16 40474004 32 ENDCOMMON 3 0 40474004 33 DATA 4 81 40474004 34 EN EN-ERR DATA ERR-T 40474004 35 MEV KEV NO-DIM PER-CENT 40474004 36 0.024 12. 1.340 2.18 40474004 37 0.040 14. 1.348 2.08 40474004 38 0.060 17. 1.336 2.03 40474004 39 0.080 21. 1.362 1.93 40474004 40 0.100 25. 1.414 1.83 40474004 41 0.115 26. 1.448 1.90 40474004 42 0.127 20. 1.472 1.40 40474004 43 0.150 20. 1.488 1.44 40474004 44 0.180 20. 1.512 1.41 40474004 45 0.210 19. 1.570 1.49 40474004 46 0.240 18. 1.603 1.43 40474004 47 0.270 18. 1.646 1.42 40474004 48 0.300 18. 1.685 1.43 40474004 49 0.320 40. 1.674 1.36 40474004 50 0.350 38. 1.686 1.41 40474004 51 0.380 37. 1.692 1.48 40474004 52 0.420 36. 1.688 1.43 40474004 53 0.460 35. 1.685 1.43 40474004 54 0.500 34. 1.685 1.38 40474004 55 0.540 33. 1.686 1.41 40474004 56 0.580 33. 1.683 1.46 40474004 57 0.620 32. 1.680 1.41 40474004 58 0.660 32. 1.682 1.40 40474004 59 0.700 32. 1.669 1.37 40474004 60 0.740 32. 1.665 1.36 40474004 61 0.780 31. 1.657 1.37 40474004 62 0.820 31. 1.643 1.36 40474004 63 0.860 31. 1.632 1.36 40474004 64 0.900 31. 1.604 1.36 40474004 65 0.950 31. 1.559 1.35 40474004 66 1.00 31. 1.544 1.34 40474004 67 1.05 34. 1.533 1.36 40474004 68 1.10 37. 1.524 1.35 40474004 69 1.15 40. 1.534 1.36 40474004 70 1.20 42. 1.521 1.36 40474004 71 1.25 44. 1.531 1.35 40474004 72 1.30 45. 1.523 1.36 40474004 73 1.35 46. 1.530 1.35 40474004 74 1.40 47. 1.519 1.34 40474004 75 1.45 48. 1.514 1.34 40474004 76 1.50 49. 1.514 1.36 40474004 77 1.60 60. 1.505 1.36 40474004 78 1.70 61. 1.501 1.38 40474004 79 1.80 63. 1.493 1.35 40474004 80 1.90 66. 1.493 1.40 40474004 81 2.00 68. 1.501 1.35 40474004 82 2.10 70. 1.506 1.36 40474004 83 2.20 71. 1.504 1.37 40474004 84 2.25 72. 1.506 1.35 40474004 85 2.30 73. 1.499 1.35 40474004 86 2.40 74. 1.504 1.36 40474004 87 2.50 75. 1.503 1.35 40474004 88 2.60 77. 1.504 1.36 40474004 89 2.70 78. 1.504 1.36 40474004 90 2.80 79. 1.508 1.36 40474004 91 2.90 82. 1.498 1.36 40474004 92 3.00 84. 1.505 1.36 40474004 93 3.10 86. 1.502 1.38 40474004 94 3.20 88. 1.494 1.36 40474004 95 3.30 91. 1.491 1.37 40474004 96 3.40 93. 1.490 1.37 40474004 97 3.60 192. 1.486 1.54 40474004 98 3.80 182. 1.488 1.47 40474004 99 4.00 146. 1.477 1.43 40474004 100 4.20 141. 1.479 1.44 40474004 101 4.40 132. 1.464 1.43 40474004 102 4.60 131. 1.453 1.44 40474004 103 4.80 125. 1.454 1.40 40474004 104 5.00 126. 1.439 1.40 40474004 105 5.20 129. 1.432 1.40 40474004 106 5.40 131. 1.430 1.39 40474004 107 5.60 135. 1.444 1.42 40474004 108 5.80 138. 1.465 1.44 40474004 109 6.00 142. 1.498 1.48 40474004 110 6.20 147. 1.496 1.50 40474004 111 6.40 152. 1.456 1.45 40474004 112 6.60 160. 1.418 1.49 40474004 113 6.80 167. 1.382 1.55 40474004 114 7.00 173. 1.341 1.53 40474004 115 7.20 178. 1.318 1.58 40474004 116 7.40 183. 1.276 1.78 40474004 117 ENDDATA 83 0 40474004 118 ENDSUBENT 117 0 4047400499999 SUBENT 40474005 20240618 421740474005 1 BIB 7 25 40474005 2 REACTION ((94-PU-241(N,F),,SIG)/(92-U-235(N,F),,SIG)) 40474005 3 SAMPLE (94-PU-241,ENR=0.9602) 40474005 4 (92-U-235,ENR=0.9997) 40474005 5 DETECTOR (IOCH) 40474005 6 MONITOR ((94-PU-241(N,F),,SIG)/(92-U-235(N,F),,SIG)) 40474005 7 Normalized to the glass detector result 40474005 8 ERR-ANALYS -Statistical error from scattering of results 40474005 9 (0.2-1.3% at 0 deg, increasing to 1.3% at 24 keV) 40474005 10 -Scattering and laboratory neutron background 40474005 11 (0.5% at 120 deg) 40474005 12 -(d,n) neutron background (<1.15%) 40474005 13 -Basic data 40474005 14 (1.9%,increasing to 2.2-2.4% at the energy rage limit)40474005 15 (ERR-T) Quadrature sum of the following errors: 40474005 16 (ERR-2,0.5,1.8) Energy dependence of fission cross 40474005 17 section ratio (0.5-1.8%)40474005 18 (ERR-3) Absolute values obtained by the glass method 40474005 19 (1.68%)40474005 20 (ERR-4) Normalization of the energy curve to the 40474005 21 reference values (0.25%)40474005 22 STATUS (TABLE,,B.I.Fursov+,J,SJA,44,262,1978)) Table 2 40474005 23 (DEP,40474002) Glass detector result 40474005 24 HISTORY (20170313A) M.M. Data were moved from Subent 003. 40474005 25 (20180724U) On. Data checked against the article. 40474005 26 (20201213A) On. ANALYSIS -> MONITOR.ERR-ANALYS revised.40474005 27 ENDBIB 25 0 40474005 28 COMMON 2 3 40474005 29 ERR-3 ERR-4 40474005 30 PER-CENT PER-CENT 40474005 31 1.68 0.25 40474005 32 ENDCOMMON 3 0 40474005 33 DATA 4 81 40474005 34 EN EN-ERR DATA ERR-T 40474005 35 MEV KEV NO-DIM PER-CENT 40474005 36 0.024 12. 1.297 2.42 40474005 37 0.040 14. 1.306 2.22 40474005 38 0.060 17. 1.296 2.19 40474005 39 0.080 21. 1.330 2.16 40474005 40 0.100 25. 1.346 2.12 40474005 41 0.115 26. 1.356 1.95 40474005 42 0.127 20. 1.360 1.83 40474005 43 0.150 20. 1.363 1.81 40474005 44 0.180 20. 1.360 1.96 40474005 45 0.210 19. 1.357 1.91 40474005 46 0.240 18. 1.379 1.82 40474005 47 0.270 18. 1.383 1.85 40474005 48 0.300 18. 1.360 1.84 40474005 49 0.320 40. 1.356 1.82 40474005 50 0.350 38. 1.339 1.82 40474005 51 0.380 37. 1.331 1.84 40474005 52 0.420 36. 1.320 1.85 40474005 53 0.460 35. 1.324 1.83 40474005 54 0.500 34. 1.325 1.83 40474005 55 0.540 33. 1.322 1.87 40474005 56 0.580 33. 1.346 1.83 40474005 57 0.620 32. 1.325 1.94 40474005 58 0.660 32. 1.320 1.84 40474005 59 0.700 32. 1.318 1.85 40474005 60 0.740 32. 1.331 1.82 40474005 61 0.780 31. 1.352 1.82 40474005 62 0.820 31. 1.357 1.83 40474005 63 0.860 31. 1.357 1.83 40474005 64 0.900 31. 1.337 1.83 40474005 65 0.950 31. 1.317 1.83 40474005 66 1.00 31. 1.302 1.82 40474005 67 1.05 34. 1.296 1.83 40474005 68 1.10 37. 1.301 1.82 40474005 69 1.15 40. 1.318 1.82 40474005 70 1.20 42. 1.332 1.82 40474005 71 1.25 44. 1.360 1.82 40474005 72 1.30 45. 1.378 1.82 40474005 73 1.35 46. 1.394 1.83 40474005 74 1.40 47. 1.406 1.82 40474005 75 1.45 48. 1.399 1.84 40474005 76 1.50 49. 1.399 1.81 40474005 77 1.60 60. 1.398 1.81 40474005 78 1.70 61. 1.379 1.84 40474005 79 1.80 63. 1.371 1.81 40474005 80 1.90 66. 1.362 1.81 40474005 81 2.00 68. 1.337 1.81 40474005 82 2.10 70. 1.324 1.81 40474005 83 2.20 71. 1.307 1.83 40474005 84 2.25 72. 1.306 1.81 40474005 85 2.30 73. 1.310 1.81 40474005 86 2.40 74. 1.289 1.84 40474005 87 2.50 75. 1.294 1.83 40474005 88 2.60 77. 1.290 1.82 40474005 89 2.70 78. 1.291 1.82 40474005 90 2.80 79. 1.289 1.82 40474005 91 2.90 82. 1.286 1.82 40474005 92 3.00 84. 1.286 1.84 40474005 93 3.10 86. 1.281 1.82 40474005 94 3.20 88. 1.278 1.82 40474005 95 3.30 91. 1.275 1.84 40474005 96 3.40 93. 1.279 1.84 40474005 97 3.60 192. 1.283 1.89 40474005 98 3.80 182. 1.286 1.97 40474005 99 4.00 146. 1.290 1.90 40474005 100 4.20 141. 1.293 1.90 40474005 101 4.40 132. 1.289 1.92 40474005 102 4.60 131. 1.295 1.90 40474005 103 4.80 125. 1.295 1.91 40474005 104 5.00 126. 1.301 1.91 40474005 105 5.20 129. 1.304 1.90 40474005 106 5.40 131. 1.318 1.89 40474005 107 5.60 135. 1.328 1.90 40474005 108 5.80 138. 1.330 1.88 40474005 109 6.00 142. 1.327 1.94 40474005 110 6.20 147. 1.319 1.91 40474005 111 6.40 152. 1.291 1.93 40474005 112 6.60 160. 1.256 1.95 40474005 113 6.80 167. 1.236 2.01 40474005 114 7.00 173. 1.221 2.05 40474005 115 7.20 178. 1.199 2.11 40474005 116 7.40 183. 1.186 2.16 40474005 117 ENDDATA 83 0 40474005 118 ENDSUBENT 117 0 4047400599999 ENDENTRY 5 0 4047499999999