ENTRY 13924 20160920 14241392400000001 SUBENT 13924001 20160920 14241392400100001 BIB 10 22 1392400100002 TITLE Measurements of the Epicadmium Capture-to-Fission 1392400100003 Cross Section Ratio in 235U 1392400100004 AUTHOR (D.E.Conway,H.D.Cook,S.B.Gunst) 1392400100005 REFERENCE (J,NSE,22,20,1965) 1392400100006 REL-REF (O,12313001,D.E.Conway+,J,NSE,29,1,1967) Continuation 1392400100007 of the current measurements. 1392400100008 INSTITUTE (1USABET) 1392400100009 FACILITY (REAC,1USABET) Beryllium reflector of the materials 1392400100010 testing reactor with a neutron flux of 8*10**14. 1392400100011 SAMPLE (92-U-235,ENR=0.93) Two samples of enriched uranium 1392400100012 6.3 wt.% in Zr in a form of 0.030 in. wire. 1392400100013 METHOD (ABSFY,INTB) The capture-to-fission ratio, alpha, for 1392400100014 the irradiation is equal to the ratio of the number 1392400100015 of 236U produced to the number of 235U nuclei 1392400100016 fission. The number of fissions can be determined from 1392400100017 the post-irradiation concentration of 137Cs as 1392400100018 measured by gamma counting. 236U concentration in the 1392400100019 sample can be determined from mass-spectrometric 1392400100020 analysis. Uranium samples were wrapped in Cd shield 1392400100021 with a cut-off threshold of 0.51 eV. 1392400100022 ERR-ANALYS (DATA-ERR) No details on sources of uncertainties. 1392400100023 HISTORY (20160920C) BP 1392400100024 ENDBIB 22 0 1392400100025 NOCOMMON 0 0 1392400100026 ENDSUBENT 25 0 1392400199999 SUBENT 13924002 20160920 14241392400200001 BIB 2 2 1392400200002 REACTION (92-U-235(N,ABS),,ALF) 1392400200003 STATUS (TABLE) page 23. 1392400200004 ENDBIB 2 0 1392400200005 NOCOMMON 0 0 1392400200006 DATA 3 1 1392400200007 EN-MIN DATA DATA-ERR 1392400200008 EV NO-DIM NO-DIM 1392400200009 0.51 0.51 0.03 1392400200010 ENDDATA 3 0 1392400200011 ENDSUBENT 10 0 1392400299999 ENDENTRY 2 0 1392499999999