ENTRY 14565 20190613 14531456500000001 SUBENT 14565001 20190613 14531456500100001 BIB 5 6 1456500100002 TITLE 238Pu Production Predictions from Available Neutron 1456500100003 Cross Sections 1456500100004 AUTHOR (E.J.Hennelly,W.R.Cornman,N.P.Baumann) 1456500100005 REFERENCE (C,68WASH,2,1271,1968) 1456500100006 INSTITUTE (1USASRL) 1456500100007 HISTORY (20190613C) BP 1456500100008 ENDBIB 6 0 1456500100009 NOCOMMON 0 0 1456500100010 ENDSUBENT 9 0 1456500199999 SUBENT 14565002 20190613 14531456500200001 BIB 6 6 1456500200002 REACTION (93-NP-237(N,G)93-NP-238,,SIG) 1456500200003 FACILITY (REAC,1USASRL) Thermal Test Reactor. 1456500200004 INC-SPECT Thermal flux of 10**15 n/cm2 sec. 1456500200005 SAMPLE Purified 237Np samples. 1456500200006 DECAY-DATA (93-NP-238,2.1D) 1456500200007 STATUS (TABLE) Table I, page 1276. 1456500200008 ENDBIB 6 0 1456500200009 NOCOMMON 0 0 1456500200010 DATA 2 1 1456500200011 EN DATA 1456500200012 EV B 1456500200013 0.0253 169.0 1456500200014 ENDDATA 3 0 1456500200015 ENDSUBENT 14 0 1456500299999 SUBENT 14565003 20190613 14531456500300001 BIB 6 6 1456500300002 REACTION (93-NP-237(N,G)93-NP-238,,RI) 1456500300003 FACILITY (REAC,1USASRL) Thermal Test Reactor. 1456500300004 INC-SPECT Thermal flux of 10**15 n/cm2 sec. 1456500300005 SAMPLE Purified 237Np samples. 1456500300006 DECAY-DATA (93-NP-238,2.1D) 1456500300007 STATUS (TABLE) Table I, page 1276. 1456500300008 ENDBIB 6 0 1456500300009 NOCOMMON 0 0 1456500300010 DATA 2 1 1456500300011 EN-MIN DATA 1456500300012 EV B 1456500300013 0.5 850.0 1456500300014 ENDDATA 3 0 1456500300015 ENDSUBENT 14 0 1456500399999 SUBENT 14565004 20190613 14531456500400001 BIB 6 7 1456500400002 REACTION (93-NP-237(N,F),,SIG) 1456500400003 FACILITY (REAC,1USASRL) Thermal Test Reactor. 1456500400004 INC-SPECT Thermal flux of 10**15 n/cm2 sec. 1456500400005 SAMPLE Purified 237Np samples. 1456500400006 METHOD From the isotopic ratio of the resultant plutonium 1456500400007 and the gamma activity of 137Cs. 1456500400008 STATUS (TABLE) Table I, page 1276. 1456500400009 ENDBIB 7 0 1456500400010 NOCOMMON 0 0 1456500400011 DATA 2 1 1456500400012 EN-DUMMY DATA 1456500400013 EV B 1456500400014 0.0253 0.02 1456500400015 ENDDATA 3 0 1456500400016 ENDSUBENT 15 0 1456500499999 SUBENT 14565005 20190613 14531456500500001 BIB 6 6 1456500500002 REACTION (92-U-236(N,G)92-U-237,,SIG) 1456500500003 FACILITY (REAC,1USASRL) Savannah River Standard Pile (SP). 1456500500004 SAMPLE 237U formed by irradiating 236U rich samples in the SP.1456500500005 METHOD Counting of gamma activity of 237U. 1456500500006 COMMENT 6.0+-0.4 b obtained in resonance integral measurement. 1456500500007 STATUS (TABLE) Table I, page 1276. 1456500500008 ENDBIB 6 0 1456500500009 NOCOMMON 0 0 1456500500010 DATA 2 1 1456500500011 EN DATA 1456500500012 EV B 1456500500013 0.0253 5.6 1456500500014 ENDDATA 3 0 1456500500015 ENDSUBENT 14 0 1456500599999 SUBENT 14565006 20190613 14531456500600001 BIB 6 6 1456500600002 REACTION (92-U-236(N,G)92-U-237,,RI) 1456500600003 FACILITY (REAC,1USASRL) Savannah River Standard Pile (SP). 1456500600004 SAMPLE 237U formed by irradiating 236U rich samples in the SP.1456500600005 METHOD Counting of gamma activity of 237U. 1456500600006 ERR-ANALYS (DATA-ERR) No details on sources of uncertainties. 1456500600007 STATUS (TABLE) Table I, page 1276. 1456500600008 ENDBIB 6 0 1456500600009 NOCOMMON 0 0 1456500600010 DATA 3 1 1456500600011 EN-MIN DATA DATA-ERR 1456500600012 EV B B 1456500600013 0.5 400.0 40.0 1456500600014 ENDDATA 3 0 1456500600015 ENDSUBENT 14 0 1456500699999 SUBENT 14565007 20190613 14531456500700001 BIB 4 5 1456500700002 REACTION ((92-U-236(N,F)92-U-237,,RI)/ 1456500700003 (92-U-236(N,G)92-U-237,,RI)) 1456500700004 FACILITY (REAC,1USASRL) Savannah River Standard Pile (SP). 1456500700005 SAMPLE 237U formed by irradiating 236U rich samples in the SP.1456500700006 STATUS (TABLE) Table I, page 1276. 1456500700007 ENDBIB 5 0 1456500700008 NOCOMMON 0 0 1456500700009 DATA 2 1 1456500700010 EN-MIN DATA 1456500700011 EV NO-DIM 1456500700012 0.5 0.005 1456500700013 ENDDATA 3 0 1456500700014 ENDSUBENT 13 0 1456500799999 ENDENTRY 7 0 1456599999999