ENTRY 20570 20180724 22752057000000001 SUBENT 20570001 20180724 22752057000100001 BIB 12 34 2057000100002 TITLE Absolute measurement of fission cross-sections of 235U,2057000100003 239Pu and 241Pu between 10 keV and 2.6 MeV 2057000100004 AUTHOR (I.Szabo, J.L.Leroy, J.P.Marquette) 2057000100005 INSTITUTE (2FR CAD) 2057000100006 REFERENCE (C,73KIEV,3,27,1973) in French 2057000100007 (C,76ANL,,208,1976) Revised (final) data in table 2057000100008 FACILITY (VDG,2FR CAD) 5 MeV Van de Graaff 2057000100009 INC-SOURCE (P-LI7) below 550 keV 2057000100010 (P-T) above 550 keV 2057000100011 DETECTOR (FISCH) 2057000100012 (BF3) Directional counters calibrated by MnSO4 bath 2057000100013 up to 2.2 MeV and associated particle method up to 2057000100014 1.5 MeV. 2057000100015 METHOD Simultaneous measure of fission events in thin 2057000100016 walled ionization chambers and neutron flux with 2057000100017 a calibrated directional counter. 2057000100018 (TOF) To discreminate scattered neutrons and parasite 2057000100019 neutrons 2057000100020 REL-REF (I,,P.H.White,J,JNE/AB,19,325,1965) 2057000100021 Description on the fissino chambers 2057000100022 (I,,J.L.Leroy+,C,70HELSINKI,1,243,1970) 2057000100023 Description on the directional counter 2057000100024 CORRECTION Corrected for 2057000100025 - background from scattered neutrons, 2057000100026 - random coincidences, 2057000100027 - non-detected fission events. 2057000100028 STATUS (TABLE) Table V in C,76ANL,,208,1976 2057000100029 HISTORY (19760303C) 2057000100030 (19790412A) Data renormalized according to reference 2057000100031 76ANL,208,197606. 2057000100032 (20140822A) SD: Corrections according last EXFOR rules 2057000100033 and Dict. Ref.73KIEV,3,27 treated as the primary 2057000100034 reference. 2057000100035 (20180724A) On. Major revisions in 002-004. 2057000100036 ENDBIB 34 0 2057000100037 NOCOMMON 0 0 2057000100038 ENDSUBENT 37 0 2057000199999 SUBENT 20570002 20180724 22752057000200001 BIB 5 14 2057000200002 REACTION (92-U-235(N,F),,SIG) 2057000200003 SAMPLE Three samples were used: 2057000200004 Isotopic composition thick- backing 2057000200005 % in atoms ness 2057000200006 U-234 U-235 U-236 U-238 mg/cm2 2057000200007 U1: 1.196 93.013 0.179 5.612 0.5 0.13mm Pt 2057000200008 U2: 0.169 99.502 0.025 0.303 0.5 0.3mm Pt 2057000200009 U3: 1.1653 97.663 0.1491 0.5229 0.5 0.6mm 2057000200010 FLAG (1.) Fission chamber with thin walls 2057000200011 (2.) Sample enriched to 97.663 atom perc. U-235. 2057000200012 ERR-ANALYS (DATA-ERR) No information on the source of uncertainty 2057000200013 (ERR-1) Uncertainty in neutron flux (1.8%) 2057000200014 HISTORY (19790412A) Updated with values from ref 76ANL,208. 2057000200015 (20180724A) On. ERR-1 added. EN-ERR -> EN-RSL-HW. 2057000200016 ENDBIB 14 0 2057000200017 COMMON 1 3 2057000200018 ERR-1 2057000200019 PER-CENT 2057000200020 1.8 2057000200021 ENDCOMMON 3 0 2057000200022 DATA 5 36 2057000200023 EN EN-RSL-HW DATA DATA-ERR FLAG 2057000200024 KEV KEV B B NO-DIM 2057000200025 17. 3. 2.420 0.080 1. 2057000200026 17. 3. 2.370 0.080 2. 2057000200027 19. 3. 2.480 0.090 2057000200028 38. 3. 1.975 0.060 1. 2057000200029 38. 3. 1.984 0.065 2. 2057000200030 40. 3. 2.047 0.070 2057000200031 51. 3. 1.849 0.050 1. 2057000200032 51. 3. 1.863 0.055 2. 2057000200033 55. 3. 1.822 0.050 2057000200034 71. 3. 1.710 0.045 1. 2057000200035 71. 3. 1.680 0.045 2. 2057000200036 75. 3. 1.707 0.050 2057000200037 88. 4. 1.556 0.040 2057000200038 124. 4. 1.580 0.040 1. 2057000200039 124. 4. 1.540 0.040 2. 2057000200040 730. 30. 1.140 0.030 2057000200041 880. 26. 1.140 0.035 1. 2057000200042 920. 26. 1.188 0.035 1. 2057000200043 1020. 25. 1.187 0.035 2057000200044 1080. 25. 1.187 0.035 2057000200045 1280. 24. 1.207 0.035 2057000200046 1405. 23. 1.229 0.035 2057000200047 1485. 22. 1.255 0.030 2057000200048 1580. 22. 1.252 0.035 2057000200049 1680. 21. 1.272 0.035 2057000200050 1800. 20. 1.306 0.035 2057000200051 1915. 20. 1.353 0.035 2057000200052 2000. 19. 1.315 0.030 2057000200053 2040. 19. 1.330 0.035 1. 2057000200054 2100. 18. 1.318 0.035 2057000200055 2180. 18. 1.294 0.035 1. 2057000200056 2190. 17. 1.303 0.030 1. 2057000200057 2280. 17. 1.304 0.030 1. 2057000200058 2300. 17. 1.293 0.030 1. 2057000200059 2380. 16. 1.275 0.032 1. 2057000200060 2610. 16. 1.270 0.030 1. 2057000200061 ENDDATA 38 0 2057000200062 ENDSUBENT 61 0 2057000299999 SUBENT 20570003 20180724 22752057000300001 BIB 4 10 2057000300002 REACTION (94-PU-239(N,F),,SIG) 2057000300003 SAMPLE 0.16 mg/cm2 thick sample on 0.3 mm Pt backing 2057000300004 238Pu, 242Pu: < 0.01% for each. 2057000300005 (94-PU-239,ENR=0.9927) 2057000300006 (94-PU-240,ENR=0.0071) 2057000300007 (94-PU-241,ENR=0.0002) 2057000300008 ERR-ANALYS (DATA-ERR) No information on the source of uncertainty 2057000300009 (ERR-1) Uncertainty in neutron flux (1.8%) 2057000300010 HISTORY (19790412A) Updated with values from ref 76ANL,208. 2057000300011 (20180724A) On. ERR-1 added. EN-ERR -> EN-RSL-HW. 2057000300012 ENDBIB 10 0 2057000300013 COMMON 1 3 2057000300014 ERR-1 2057000300015 PER-CENT 2057000300016 1.8 2057000300017 ENDCOMMON 3 0 2057000300018 DATA 4 20 2057000300019 EN EN-RSL-HW DATA DATA-ERR 2057000300020 KEV KEV B B 2057000300021 805. 27. 1.564 0.045 2057000300022 880. 26. 1.660 0.050 2057000300023 920. 26. 1.706 0.050 2057000300024 1190. 25. 1.856 0.050 2057000300025 1280. 24. 1.823 0.045 2057000300026 1405. 23. 1.876 0.047 2057000300027 1465. 23. 1.969 0.050 2057000300028 1485. 22. 1.900 0.048 2057000300029 1580. 22. 1.906 0.050 2057000300030 1680. 21. 1.973 0.055 2057000300031 1800. 20. 1.979 0.050 2057000300032 2000. 19. 1.967 0.060 2057000300033 2040. 19. 2.034 0.055 2057000300034 2100. 18. 2.040 0.055 2057000300035 2180. 18. 1.979 0.055 2057000300036 2190. 17. 1.986 0.055 2057000300037 2230. 17. 2.025 0.055 2057000300038 2300. 17. 1.960 0.050 2057000300039 2380. 16. 1.897 0.060 2057000300040 2610. 16. 1.916 0.050 2057000300041 ENDDATA 22 0 2057000300042 ENDSUBENT 41 0 2057000399999 SUBENT 20570004 20180724 22752057000400001 BIB 4 11 2057000400002 REACTION (94-PU-241(N,F),,SIG) 2057000400003 SAMPLE 0.13 mg/cm2 thick sample on 0.3 mm Pt backing. 2057000400004 239Pu: < 0.01% 2057000400005 (94-PU-241,ENR=0.94658) 2057000400006 (94-PU-239,ENR=0.00868) 2057000400007 (94-PU-240,ENR=0.02968) 2057000400008 (94-PU-242,ENR=0.01497) 2057000400009 ERR-ANALYS (DATA-ERR) No information on the source of uncertainty 2057000400010 (ERR-1) Uncertainty in neutron flux (1.8%) 2057000400011 HISTORY (19790412A) Updated with values from ref 76ANL,208. 2057000400012 (20180724A) On. ERR-1 added. EN-ERR -> EN-RSL-HW. 2057000400013 ENDBIB 11 0 2057000400014 COMMON 1 3 2057000400015 ERR-1 2057000400016 PER-CENT 2057000400017 1.8 2057000400018 ENDCOMMON 3 0 2057000400019 DATA 4 6 2057000400020 EN EN-RSL-HW DATA DATA-ERR 2057000400021 KEV KEV B B 2057000400022 1180. 25. 1.620 0.045 2057000400023 1470. 22. 1.707 0.050 2057000400024 1700. 21. 1.739 0.050 2057000400025 2010. 19. 1.700 0.050 2057000400026 2240. 17. 1.613 0.050 2057000400027 2630. 16. 1.569 0.055 2057000400028 ENDDATA 8 0 2057000400029 ENDSUBENT 28 0 2057000499999 ENDENTRY 4 0 2057099999999