ENTRY 12474 20220210 14981247400000001 SUBENT 12474001 20220210 14981247400100001 BIB 9 23 1247400100002 TITLE The neutron-induced fission cross section of U-236 as 1247400100003 a function of energy 1247400100004 AUTHOR (W.Nyer) 1247400100005 REFERENCE (R,LA-1258,1951) 1247400100006 INSTITUTE (1USALAS) 1247400100007 FACILITY (CCW,1USALAS) The Z Building Cockcroft-Walton 1247400100008 accelerator. 1247400100009 (VDG,1USALAS) 1247400100010 INC-SOURCE (P-T,D-D,D-T) For energies between 690 and 1320 1247400100011 keV, the VDG accelerator with the reaction (P-T) was 1247400100012 used. The 2.55 and 14.1 MeV neutrons by means of the 1247400100013 D(d,n)He3 and T(d,n)He4 reactions, respectively. 1247400100014 SAMPLE Uranium foils prepared by John Povelites of Group 1247400100015 CMR-4. 1247400100016 CORRECTION A correction of about 3% was applied for the effect 1247400100017 of low energy epi-cadmium neutrons in the 14.1 MeV 1247400100018 measurement. 1247400100019 HISTORY (19760804T) Translated from SCISRS. 1247400100020 (19830809A) Converted to reaction formalism. 1247400100021 (20220210A) BP: Updated to new date formats, lower 1247400100022 case. Corrections according last EXFOR rules and 1247400100023 Dict. Added facility, incoming source, correction, 1247400100024 error analysis. 1247400100025 ENDBIB 23 0 1247400100026 NOCOMMON 0 0 1247400100027 ENDSUBENT 26 0 1247400199999 SUBENT 12474002 20220210 14981247400200001 BIB 5 13 1247400200002 REACTION ((92-U-236(N,F),,SIG)/(92-U-235(N,F),,SIG)) 1247400200003 METHOD The measurements consisted of determining the ratio 1247400200004 of the number of fissions in the 236U foil to the 1247400200005 number of fissions in the 235U foil when the chamber 1247400200006 was placed in a flux of neutrons of known energy E. 1247400200007 ERR-ANALYS (ERR-S) Statistical errors. No estimate of the errors 1247400200008 in the cross section due to the presence of low 1247400200009 energy epi-cadmium neutrons was made for any 1247400200010 measurement except the 14.1 MeV case. It is 1247400200011 believed that this error is small. 1247400200012 STATUS (TABLE) Table I, page 8. 1247400200013 HISTORY (20220210A) BP: Changed DATA-ERR to ERR-S, added 1247400200014 method. 1247400200015 ENDBIB 13 0 1247400200016 NOCOMMON 0 0 1247400200017 DATA 5 6 1247400200018 EN +EN-RSL -EN-RSL DATA ERR-S 1247400200019 MEV MEV MEV NO-DIM NO-DIM 1247400200020 6.90E-01 3.4E-02 3.4E-02 3.E-02 6.E-02 1247400200021 7.70E-01 3.5E-02 4.0E-02 1.4E-01 6.E-02 1247400200022 1.000 4.0E-02 5.0E-02 2.7E-01 5.E-02 1247400200023 1.320 3.3E-02 5.2E-02 5.2E-01 7.E-02 1247400200024 2.55 8.E-02 8.E-02 4.0E-01 4.E-02 1247400200025 1.41E+01 1.E-01 1.E-01 7.1E-01 3.E-02 1247400200026 ENDDATA 8 0 1247400200027 ENDSUBENT 26 0 1247400299999 SUBENT 12474003 20220210 14981247400300001 BIB 6 11 1247400300002 REACTION (92-U-236(N,F),,SIG) 1247400300003 REL-REF (R,12306004,W.Nyer,R,LAMS-938,1950) 235U data. 1247400300004 (R,12514002,W.Nyer,R,LA-719,1948) 238U data. 1247400300005 (R,12312004,J.H.Williams,R,LA-520,1946) U238/U235 data.1247400300006 ANALYSIS Used known 235,238U cross sections to deduce 236U 1247400300007 cross sections. 1247400300008 ERR-ANALYS (DATA-ERR) No details on sources of uncertainties. 1247400300009 STATUS (DEP,12474002) 1247400300010 (TABLE) Table I, page 8. 1247400300011 HISTORY (20220210A) BP: Changed monitor to analysis, added 1247400300012 related references. 1247400300013 ENDBIB 11 0 1247400300014 NOCOMMON 0 0 1247400300015 DATA 5 6 1247400300016 EN +EN-RSL -EN-RSL DATA DATA-ERR 1247400300017 MEV MEV MEV B B 1247400300018 6.90E-01 3.4E-02 3.4E-02 4.E-02 8.E-02 1247400300019 7.70E-01 3.5E-02 4.0E-02 1.9E-01 8.E-02 1247400300020 1.000 4.0E-02 5.0E-02 3.6E-01 7.E-02 1247400300021 1.320 3.3E-02 5.2E-02 6.9E-01 1.0E-01 1247400300022 2.55 8.E-02 8.E-02 5.3E-01 6.E-02 1247400300023 1.41E+01 1.E-01 1.E-01 1.65 1.0E-01 1247400300024 ENDDATA 8 0 1247400300025 ENDSUBENT 24 0 1247400399999 ENDENTRY 3 0 1247499999999