ENTRY 20567 20180724 22752056700000001 SUBENT 20567001 20180724 22752056700100001 BIB 13 41 2056700100002 TITLE New absolute measurement of the neutron-induced 2056700100003 fission cross sections of 235U, 239Pu, and 241Pu from 2056700100004 17 keV to 1 MeV 2056700100005 AUTHOR (I.Szabo, G.Filippi, J.L.Huet, J.L.Leroy, 2056700100006 J.P.Marquette) 2056700100007 INSTITUTE (2FR CAD) 2056700100008 REFERENCE (C,70ANL,,257,1970) 2056700100009 (C,76ANL,,208,1976) Revised (final) data in table 2056700100010 (C,70HELSINKI,1,229,1970) Prelim. data in table 2056700100011 REL-REF (O,20569001,I.Szabo+,C,71KNOX,2,573,1971) 2056700100012 (O,20570001,I.Szabo+,C,73KIEV,3,27,1973) 2056700100013 (O,20618001,I.Szabo+,C,76ANL,,208,1976) 2056700100014 FACILITY (VDG,2FR CAD) 5 MeV Van de Graaff 2056700100015 INC-SOURCE (P-LI7) below 550 keV 2056700100016 (P-T) above 550 keV 2056700100017 INC-SPECT Energy spreads varied from 3 keV at 25 keV neutron 2056700100018 energy to 16 keV at 540 keV neutron energy. 2056700100019 METHOD (TOF) for background supression 2056700100020 DETECTOR (FISCH) 2056700100021 (BF3) Calibrated by the associated particle method, 2056700100022 manganese sulphate bath method and proton recoil 2056700100023 counter method. 2056700100024 CORRECTION Corrected for 2056700100025 - extrapolation of fission fragment spectrum to 2056700100026 zero bias 2056700100027 - fission fragment loss in foil 2056700100028 - scattering in chamber structure 2056700100029 - distance 2056700100030 - background in fission chamber 2056700100031 - air attenuation 2056700100032 STATUS (TABLE) Table III in C,76ANL,,208,1976 2056700100033 HISTORY (19720530C) 2056700100034 (19760304A) Comment modified. 2056700100035 (19790418A) Data recalculated. See ref 76ANL,208. 2056700100036 (20140822A) SD: Updated to new date formats,lower case.2056700100037 Corrections according last EXFOR rules and Dict. 2056700100038 Ref. 70ANL,257 treated as the primary reference. 2056700100039 SAMPLE was added in Sub. 2-4. 2056700100040 (20170724A) On. ERR-ANALYS moved to 002-004. Major rev.2056700100041 002,003 and 004. 2056700100042 (20180724A) On. Major revision in 002-004. 2056700100043 ENDBIB 41 0 2056700100044 NOCOMMON 0 0 2056700100045 ENDSUBENT 44 0 2056700199999 SUBENT 20567002 20180724 22752056700200001 BIB 4 18 2056700200002 REACTION (92-U-235(N,F),,SIG) 2056700200003 SAMPLE Three samples used: 2056700200004 1. U3O8 0.5 mg/cm2 thick on 0.13 mm Pt backing. 2056700200005 Isotop.comp.: 234U - 1.196%, 235U - 93.013%, 2056700200006 236U - 0.179%, 238U - 5.612%. 2056700200007 1. U3O8 0.5 mg/cm2 thick on 0.3 mm Pt backing. 2056700200008 Isotop.comp.: 234U - 0.169%, 235U - 99.502%, 2056700200009 236U - 0.025%, 238U - 0.303%. 2056700200010 1. U3O8 0.5 mg/cm2 thick on 0.6 mm quartz backing. 2056700200011 Isotop.comp.: 234U - 1.1653%, 235U - 97.663%, 2056700200012 236U - 0.1491%, 238U - 0.5229%. 2056700200013 ERR-ANALYS (DATA-ERR) No information on the source of uncertainty 2056700200014 (Table II of C,70HELSINKI,1,229,1970 summarizes 2056700200015 partial uncertainties of preliminary data at 68 keV) 2056700200016 (ERR-1) Uncertainty in neutron flux (1.8%) 2056700200017 HISTORY (20170724A) On. ERR-ANALYS moved from 001 and updated. 2056700200018 Numerical data checked against the article table. 2056700200019 (20180724A) On. ERR-1 added. EN-RSL -> EN-RSL-HW. 2056700200020 ENDBIB 18 0 2056700200021 COMMON 1 3 2056700200022 ERR-1 2056700200023 PER-CENT 2056700200024 1.8 2056700200025 ENDCOMMON 3 0 2056700200026 DATA 4 31 2056700200027 EN EN-RSL-HW DATA DATA-ERR 2056700200028 KEV KEV B B 2056700200029 17.5 3.5 2.150 0.090 2056700200030 27. 3.5 2.10 0.080 2056700200031 42. 5. 1.80 0.060 2056700200032 68. 5. 1.765 0.045 2056700200033 72.5 6.5 1.740 0.055 2056700200034 95. 5. 1.540 0.055 2056700200035 110. 10. 1.530 0.050 2056700200036 120. 8. 1.570 0.055 2056700200037 125. 7. 1.500 0.050 2056700200038 145. 9. 1.500 0.055 2056700200039 150. 6. 1.450 0.045 2056700200040 152. 10. 1.440 0.040 2056700200041 154. 14. 1.440 0.035 2056700200042 156. 12. 1.450 0.045 2056700200043 195. 11. 1.365 0.055 2056700200044 215. 10. 1.325 0.045 2056700200045 227. 16. 1.295 0.035 2056700200046 251. 11. 1.285 0.035 2056700200047 257. 15. 1.275 0.055 2056700200048 272. 15. 1.275 0.045 2056700200049 286. 15. 1.270 0.035 2056700200050 313. 15. 1.285 0.045 2056700200051 320. 8. 1.190 0.045 2056700200052 331. 15. 1.210 0.045 2056700200053 369. 15. 1.215 0.045 2056700200054 407. 15. 1.205 0.035 2056700200055 506. 17. 1.160 0.030 2056700200056 540. 10. 1.160 0.045 2056700200057 665. 22. 1.140 0.035 2056700200058 810. 35. 1.135 0.035 2056700200059 1010. 40. 1.205 0.035 2056700200060 ENDDATA 33 0 2056700200061 ENDSUBENT 60 0 2056700299999 SUBENT 20567003 20180724 22752056700300001 BIB 4 15 2056700300002 REACTION (94-PU-239(N,F),,SIG) 2056700300003 SAMPLE Two samples: 2056700300004 0.15 mg/cm2 thick sample on 0.3 mm Pt backing, 2056700300005 0.17 mg/cm2 thick sample on 0.13 mm Pt backing. 2056700300006 238Pu, 242Pu: < 0.01% for each. 2056700300007 (94-PU-239,ENR=0.9927) 2056700300008 (94-PU-240,ENR=0.0071) 2056700300009 (94-PU-241,ENR=0.0002) 2056700300010 ERR-ANALYS (DATA-ERR) No information on the source of uncertainty 2056700300011 (Table II of C,70HELSINKI,1,229,1970 summarizes 2056700300012 partial uncertainties of preliminary data at 506 keV)2056700300013 (ERR-1) Uncertainty in neutron flux (1.8%) 2056700300014 HISTORY (20170724A) On. ERR-ANALYS moved from 001 and updated. 2056700300015 Numerical data checked against the article table. 2056700300016 (20180724A) On. ERR-1 added. EN-RSL -> EN-RSL-HW. 2056700300017 ENDBIB 15 0 2056700300018 COMMON 1 3 2056700300019 ERR-1 2056700300020 PER-CENT 2056700300021 1.8 2056700300022 ENDCOMMON 3 0 2056700300023 DATA 4 21 2056700300024 EN EN-RSL-HW DATA DATA-ERR 2056700300025 KEV KEV B B 2056700300026 35. 4. 1.530 0.070 2056700300027 49. 5. 1.495 0.060 2056700300028 57. 8. 1.505 0.050 2056700300029 73. 7. 1.540 0.055 2056700300030 77.5 8. 1.530 0.055 2056700300031 102. 8. 1.565 0.055 2056700300032 109. 8. 1.500 0.050 2056700300033 135. 5. 1.470 0.050 2056700300034 152. 10. 1.440 0.040 2056700300035 154. 7. 1.475 0.040 2056700300036 165. 13. 1.420 0.040 2056700300037 197. 16. 1.420 0.040 2056700300038 226. 12. 1.400 0.055 2056700300039 251. 10. 1.480 0.040 2056700300040 331. 12. 1.545 0.035 2056700300041 377. 9. 1.530 0.035 2056700300042 453. 13. 1.570 0.040 2056700300043 506. 16. 1.590 0.040 2056700300044 665. 22. 1.595 0.04 2056700300045 810. 35. 1.700 0.04 2056700300046 972. 40. 1.720 0.04 2056700300047 ENDDATA 23 0 2056700300048 ENDSUBENT 47 0 2056700399999 SUBENT 20567004 20180724 22752056700400001 BIB 4 14 2056700400002 REACTION (94-PU-241(N,F),,SIG) 2056700400003 SAMPLE Two samples: 2056700400004 0.72 mg/cm2 thick sample on 0.3 mm Pt backing, 2056700400005 0.13 mg/cm2 thick sample on 0.3 mm Pt backing. 2056700400006 239Pu: < 0.01% 2056700400007 (94-PU-241,ENR=0.94658) 2056700400008 (94-PU-239,ENR=0.00868) 2056700400009 (94-PU-240,ENR=0.02968) 2056700400010 (94-PU-242,ENR=0.01497) 2056700400011 ERR-ANALYS (DATA-ERR) No information on the source of uncertainty 2056700400012 (ERR-1) Uncertainty in neutron flux (1.8%) 2056700400013 HISTORY (20170724A) On. ERR-ANALYS moved from 001 and updated. 2056700400014 Numerical data checked against the article table. 2056700400015 (20180724A) On. ERR-1 added. EN-RSL -> EN-RSL-HW. 2056700400016 ENDBIB 14 0 2056700400017 COMMON 1 3 2056700400018 ERR-1 2056700400019 PER-CENT 2056700400020 1.8 2056700400021 ENDCOMMON 3 0 2056700400022 DATA 4 15 2056700400023 EN EN-RSL-HW DATA DATA-ERR 2056700400024 KEV KEV B B 2056700400025 35. 4. 2.64 0.13 2056700400026 50. 5. 2.39 0.12 2056700400027 88. 4. 2.06 0.11 2056700400028 130. 20. 2.02 0.11 2056700400029 177. 10. 1.91 0.09 2056700400030 218. 8. 1.71 0.08 2056700400031 239. 7. 1.72 0.08 2056700400032 300. 12. 1.59 0.07 2056700400033 344. 10. 1.56 0.07 2056700400034 463. 12. 1.44 0.07 2056700400035 476. 10. 1.50 0.07 2056700400036 604. 30. 1.42 0.06 2056700400037 687. 29. 1.41 0.06 2056700400038 808. 29. 1.49 0.07 2056700400039 970. 25. 1.52 0.07 2056700400040 ENDDATA 17 0 2056700400041 ENDSUBENT 40 0 2056700499999 ENDENTRY 4 0 2056799999999