ENTRY 12585 20210920 14871258500000001 SUBENT 12585001 20210920 14871258500100001 BIB 11 36 1258500100002 TITLE Curium Isotopes 246 and 247 from Pile-Irradiated 1258500100003 Plutonium 1258500100004 AUTHOR (C.M.Stevens,M.H.Studier,P.R.Fields,J.F.Mech, 1258500100005 P.A.Sellers,A.M.Friedman,H.Diamond,J.R.Huizenga) 1258500100006 REFERENCE (J,PR,94,974,1954) 1258500100007 #doi:10.1103/PhysRev.94.974 1258500100008 INSTITUTE (1USAANL) 1258500100009 FACILITY (REAC,1USAANL) The Materials Testing Reactor (MTR). 1258500100010 INC-SPECT Reactor spectrum. 1258500100011 SAMPLE Sample I, Total flux 4x10**21 neutrons. 1258500100012 Sample II, Total flux 8x10**21 neutrons. 1258500100013 (96-CM-242,ENR=0.168) Sample I 1258500100014 (96-CM-244,ENR=0.821) Sample I 1258500100015 (96-CM-245,ENR=0.0093) Sample I 1258500100016 (96-CM-246,ENR=0.0024) Sample I 1258500100017 (96-CM-242,ENR=0.0184) Sample II 1258500100018 (96-CM-244,ENR=0.9551) Sample II 1258500100019 (96-CM-245,ENR=0.0127) Sample II 1258500100020 (96-CM-246,ENR=0.0136) Sample II 1258500100021 (96-CM-247,ENR=0.00016) Sample II 1258500100022 METHOD (CHSEP,ASEP) The curium produced by the irradiation 1258500100023 of two plutonium samples (total integrated fluxes 1258500100024 4x10**21 and 8x10**21 neutrons) in the Materials 1258500100025 Testing Reactor (MTR) was chemically purified from 1258500100026 fission products and other actinide elements. The 1258500100027 curium samples were analyzed in a 12-in., 60 degree 1258500100028 mass spectrometer with a multiple filament source. 1258500100029 ERR-ANALYS (DATA-ERR) No details on sources of uncertainties. 1258500100030 STATUS (TABLE) page 974. 1258500100031 HISTORY (19760804T) Translated from SCISRS 1258500100032 (19841024A) BIB corrections. 1258500100033 (19860609A) BIB update. 1258500100034 (20200430A) BP: Updated to new date formats, lower 1258500100035 case and BIB section. Corrections according 1258500100036 last EXFOR rules and Dict. 1258500100037 (20210901A) OS. Data correction in sub.2 1258500100038 ENDBIB 36 0 1258500100039 NOCOMMON 0 0 1258500100040 ENDSUBENT 39 0 1258500199999 SUBENT 12585002 20210920 14871258500200001 BIB 5 6 1258500200002 REACTION (95-AM-243(N,G)95-AM-244,,SIG,,SPA) 1258500200003 METHOD (BURN) Calculated from the relative quantities of Am2431258500200004 and Cm244 present at the end of the irradiations 1258500200005 DECAY-DATA (96-CM-244,19.2YR) Deduced by authors. 1258500200006 ASSUMED (ASSUM,96-CM-244(N,G)96-CM-245,,SIG) 1258500200007 HISTORY (20210901A) DATA-ERR value corrected 1258500200008 ENDBIB 6 0 1258500200009 COMMON 1 3 1258500200010 ERR-HL 1258500200011 YR 1258500200012 0.6 1258500200013 ENDCOMMON 3 0 1258500200014 DATA 4 1 1258500200015 EN-DUMMY DATA DATA-ERR ASSUM 1258500200016 MEV B B B 1258500200017 2.53E-08 1.15E+02 20. 25. 1258500200018 ENDDATA 3 0 1258500200019 ENDSUBENT 18 0 1258500299999 SUBENT 12585003 20200430 14711258500300001 BIB 1 1 1258500300002 REACTION (96-CM-244(N,G)96-CM-245,,SIG,,SPA) 1258500300003 ENDBIB 1 0 1258500300004 NOCOMMON 0 0 1258500300005 DATA 3 1 1258500300006 EN-DUMMY DATA DATA-ERR 1258500300007 MEV B B 1258500300008 2.53E-08 2.5E+01 1.0E+01 1258500300009 ENDDATA 3 0 1258500300010 ENDSUBENT 9 0 1258500399999 SUBENT 12585004 20200430 14711258500400001 BIB 1 1 1258500400002 REACTION (96-CM-245(N,G)96-CM-246,,SIG,,SPA) 1258500400003 ENDBIB 1 0 1258500400004 NOCOMMON 0 0 1258500400005 DATA 3 1 1258500400006 EN-DUMMY DATA DATA-ERR 1258500400007 MEV B B 1258500400008 2.53E-08 2.00E+02 1.00E+02 1258500400009 ENDDATA 3 0 1258500400010 ENDSUBENT 9 0 1258500499999 SUBENT 12585005 20200430 14711258500500001 BIB 1 1 1258500500002 REACTION (96-CM-246(N,G)96-CM-247,,SIG,,SPA) 1258500500003 ENDBIB 1 0 1258500500004 NOCOMMON 0 0 1258500500005 DATA 3 1 1258500500006 EN-DUMMY DATA DATA-ERR 1258500500007 MEV B B 1258500500008 2.53E-08 1.5E+01 1.0E+01 1258500500009 ENDDATA 3 0 1258500500010 ENDSUBENT 9 0 1258500599999 ENDENTRY 5 0 1258599999999