ENTRY 20569 20170724 22622056900000001 SUBENT 20569001 20170724 22622056900100001 BIB 12 38 2056900100002 TITLE 235U fission cross section from 10 keV to 200 keV 2056900100003 AUTHOR (I.Szabo, G.Filippi, J.L.Huet, J.L.Leroy, 2056900100004 J.P.Marquette) 2056900100005 INSTITUTE (2FR CAD) 2056900100006 REFERENCE (C,71KNOX,2,573,1971) 2056900100007 (C,76ANL,,208,1976) Revised (final) 235U data in table 2056900100008 REL-REF (O,20567001,I.Szabo+,C,76ANL,,208,1976) 2056900100009 (M,,J.L.Leroy+,C,70HELSINKI,1,243,1970) 2056900100010 Methods for the absolute measurements of fast neutron 2056900100011 fluxes by flat response counter 2056900100012 (M,20570001,I.Szabo+,C,73KIEV,3,27,1973) 2056900100013 Explanation of renormalization 2056900100014 FACILITY (VDG,2FR CAD) Cadarache 5 MeV Van de Graaff accelerator2056900100015 INC-SOURCE (P-LI7) 2056900100016 METHOD (TOF) for background supression 2056900100017 DETECTOR (FISCH) Fast response ionization chamber 2056900100018 (BF3) Flat response counter calibrated by the 2056900100019 associated particle method and the manganese sulphate 2056900100020 bath method 2056900100021 CORRECTION Corrected for 2056900100022 - extrapolation of fission fragment spectrum to 2056900100023 zero bias 2056900100024 - fission fragment loss in foil 2056900100025 - scattering in chamber structure 2056900100026 - scattering in target assembly 2056900100027 - background in fission chamber 2056900100028 - air attenuation 2056900100029 STATUS (TABLE) Table IV of C,76ANL,,208,1976. 2056900100030 HISTORY (19710608C) 2056900100031 (19760303A) Comment changed. 2056900100032 (19760423E) 2056900100033 (19790419A) Updated with values from ref 76ANL,208. 2056900100034 (19790518E) 2056900100035 (20140822A) SD: Updated to new date formats,lower case.2056900100036 Corrections according last EXFOR rules and Dict. 2056900100037 Ref. 71KNOX,2,573 treated as the primary reference. 2056900100038 ERR-ANALYS moved to Subents 2,3. 2056900100039 (20170724A) On. Major revisions in 002-004. 2056900100040 ENDBIB 38 0 2056900100041 NOCOMMON 0 0 2056900100042 ENDSUBENT 41 0 2056900199999 SUBENT 20569002 20170724 22622056900200001 BIB 5 23 2056900200002 REACTION (92-U-235(N,F),,SIG) 2056900200003 SAMPLE Uranium oxide deposit prepared and assayed by CBMN 2056900200004 ERR-ANALYS (DATA-ERR) Total uncertainty includes: 2056900200005 - Number of atoms (0.8% at 58 keV)2056900200006 - Extrapolation of fission fragments spectrum to 2056900200007 zero bias (0.3% at 58 keV)2056900200008 - Fission fragments lost in foil (0.4% at 58 keV)2056900200009 - Scattering in chamber structure (0.4% at 58 keV)2056900200010 - Scattering in target assembly (0.3% at 58 keV)2056900200011 - Background in fission chamber (0.3% at 58 keV)2056900200012 - Air attenuation (0.5% at 58 keV)2056900200013 - Neutron flux determination (1.8% at 58 keV)2056900200014 - Statistics (0.8% at 58 keV)2056900200015 - Distances measurements (0.2% at 58 keV)2056900200016 COMMENT Cross section in Table 1 of 71KNOX,2,573 have been 2056900200017 multiplied by a factor of 1.02 taking account of 2056900200018 a revised half-life of U-234 and the fragment 2056900200019 absorption. 2056900200020 This modification of cross section was originally 2056900200021 done at CCDN. 2056900200022 HISTORY (19760304A) Updated with values from ref 76ANL,208. 2056900200023 (20170724A) On. Data renormalized by CCDN replaced 2056900200024 with those published in the article. EN-RSL->EN-RS-HW 2056900200025 ENDBIB 23 0 2056900200026 NOCOMMON 0 0 2056900200027 DATA 4 15 2056900200028 EN EN-RSL DATA DATA-ERR 2056900200029 KEV KEV B B 2056900200030 11.5 3. 2.76 0.09 2056900200031 15.0 3. 2.50 0.07 2056900200032 22.5 2.5 2.20 0.06 2056900200033 33.0 5. 2.02 0.06 2056900200034 46.0 5. 1.85 0.05 2056900200035 58.0 3. 1.83 0.05 2056900200036 78.0 2.5 1.70 0.05 2056900200037 83.5 11. 1.65 0.05 2056900200038 93.0 4. 1.55 0.04 2056900200039 103.5 5.5 1.53 0.04 2056900200040 116. 15. 1.52 0.04 2056900200041 135. 5. 1.42 0.04 2056900200042 150. 5. 1.46 0.04 2056900200043 172. 5.5 1.46 0.04 2056900200044 199. 5.5 1.42 0.040 2056900200045 ENDDATA 17 0 2056900200046 ENDSUBENT 45 0 2056900299999 SUBENT 20569003 20170724 22622056900300001 BIB 4 15 2056900300002 REACTION (94-PU-239(N,F),,SIG) 2056900300003 SAMPLE Plutonium oxide deposit prepared and assayed by CBMN 2056900300004 ERR-ANALYS (DATA-ERR) Total uncertainty includes: 2056900300005 - Number of atoms (0.6% at 58 keV)2056900300006 - Extrapolation of fission fragments spectrum to 2056900300007 zero bias (0.3% at 58 keV)2056900300008 - Fission fragments lost in foil (0.3% at 58 keV)2056900300009 - Scattering in chamber structure (0.4% at 58 keV)2056900300010 - Scattering in target assembly (0.2% at 58 keV)2056900300011 - Background in fission chamber (0.5% at 58 keV)2056900300012 - Air attenuation (0.5% at 58 keV)2056900300013 - Neutron flux determination (1.8% at 58 keV)2056900300014 - Statistics (1.5% at 58 keV)2056900300015 - Distances measurements (0.2% at 58 keV)2056900300016 HISTORY (20170724A) On. EN-RSL -> EN-RSL-HW 2056900300017 ENDBIB 15 0 2056900300018 NOCOMMON 0 0 2056900300019 DATA 4 15 2056900300020 EN EN-RSL-HW DATA DATA-ERR 2056900300021 KEV KEV B B 2056900300022 11.5 3. 1.778 0.058 2056900300023 15.0 3. 1.75 0.052 2056900300024 22.5 2.5 1.71 0.06 2056900300025 33.0 5. 1.59 0.04 2056900300026 46.0 5. 1.59 0.04 2056900300027 58.0 3. 1.55 0.04 2056900300028 78.0 2.5 1.55 0.05 2056900300029 83.5 11. 1.53 0.04 2056900300030 93.0 4. 1.58 0.04 2056900300031 103.5 5.5 1.54 0.04 2056900300032 116. 15. 1.59 0.04 2056900300033 135. 5. 1.46 0.05 2056900300034 150. 5. 1.49 0.04 2056900300035 172. 5.5 1.48 0.04 2056900300036 199. 5.5 1.49 0.04 2056900300037 ENDDATA 17 0 2056900300038 ENDSUBENT 37 0 2056900399999 SUBENT 20569004 20170724 22622056900400001 BIB 5 11 2056900400002 REACTION ((94-PU-239(N,F),,SIG)/(92-U-235(N,F),,SIG)) 2056900400003 ANALYSIS The ratio can be determined because 235U(n,f) and 2056900400004 239Pu(n,f) were measured simultaneously. 2056900400005 Ratios in Table 1 of 71KNOX,2,573 have been multiplied 2056900400006 by a factor of 0.98 taking account of a revised 2056900400007 half-life of U-234 and the fragment absorption. 2056900400008 ERR-ANALYS (DATA-ERR) No information on the source of uncertainty 2056900400009 STATUS (DEP,20569002) 235U(n,f) 2056900400010 (DEP,20569003) 239Pu(n,f) 2056900400011 HISTORY (19760304A) Updated with values from ref 76ANL,208. 2056900400012 (20170724A) On. EN-RSL -> EN-RSL-HW 2056900400013 ENDBIB 11 0 2056900400014 NOCOMMON 0 0 2056900400015 DATA 4 15 2056900400016 EN EN-RSL-HW DATA DATA-ERR 2056900400017 KEV KEV NO-DIM NO-DIM 2056900400018 11.5 3. 0.646 0.022 2056900400019 15.0 3. 0.704 0.021 2056900400020 22.5 2.5 0.773 0.030 2056900400021 33.0 5. 0.789 0.020 2056900400022 46.0 5. 0.858 0.024 2056900400023 58.0 3. 0.850 0.023 2056900400024 78.0 2.5 0.911 0.027 2056900400025 83.5 11. 0.926 0.024 2056900400026 93.0 4. 1.015 0.026 2056900400027 103.5 5.5 1.005 0.024 2056900400028 116. 15. 0.997 0.022 2056900400029 135. 5. 1.034 0.034 2056900400030 150. 5. 1.017 0.030 2056900400031 172. 5.5 1.017 0.026 2056900400032 199. 5.5 1.041 0.027 2056900400033 ENDDATA 17 0 2056900400034 ENDSUBENT 33 0 2056900499999 ENDENTRY 4 0 2056999999999