ENTRY 12583 20080624 13491258300000001 SUBENT 12583001 20080624 13491258300100001 BIB 7 10 1258300100002 INSTITUTE (1USABRK) 1258300100003 REFERENCE (J,PR,85,135,1952) 1258300100004 AUTHOR (K.Street Jr,A.Ghiorso,S.G.Thompson) 1258300100005 TITLE Slow Neutron Fission of Am242,Am242m, and Am243. 1258300100006 FACILITY (REAC) 1258300100007 STATUS (OUTDT) 1258300100008 (SCSRS) 1258300100009 HISTORY (19760804T) Translated from SCISRS 1258300100010 (20080624A) Converted to new date formats, lower case. 1258300100011 BIB updates. 1258300100012 ENDBIB 10 0 1258300100013 NOCOMMON 0 0 1258300100014 ENDSUBENT 13 0 1258300199999 SUBENT 12583002 20080624 13491258300200001 BIB 4 6 1258300200002 REACTION (95-AM-241(N,G)95-AM-242-M,,SIG,,SPA) 1258300200003 INC-SPECT Reactor spectrum 1258300200004 METHOD (MASSP) Mass spectrometer 1258300200005 ANALYSIS Reanalysis of previously irradiated americium sample. 1258300200006 Principle uncertainties are in estimation of neutron 1258300200007 flux. 1258300200008 ENDBIB 6 0 1258300200009 NOCOMMON 0 0 1258300200010 DATA 2 1 1258300200011 EN-DUMMY DATA-APRX 1258300200012 MEV B 1258300200013 2.53 -08 5.0 +01 1258300200014 ENDDATA 3 0 1258300200015 ENDSUBENT 14 0 1258300299999 SUBENT 12583003 20080624 13491258300300001 BIB 4 4 1258300300002 REACTION (95-AM-241(N,G)95-AM-242-G,,SIG,,SPA) 1258300300003 INC-SPECT Reactor spectrum 1258300300004 METHOD (ACTIV) Activation 1258300300005 DECAY-DATA (95-AM-242-G,16.HR,B-,,0.60) 1258300300006 ENDBIB 4 0 1258300300007 NOCOMMON 0 0 1258300300008 DATA 2 1 1258300300009 EN-DUMMY DATA-APRX 1258300300010 MEV B 1258300300011 2.53 -08 3.00 +02 1258300300012 ENDDATA 3 0 1258300300013 ENDSUBENT 12 0 1258300399999 SUBENT 12583004 20080624 13491258300400001 BIB 5 8 1258300400002 REACTION (95-AM-242(N,F),,SIG,,MXW) 1258300400003 INC-SPECT Thermal spectrum 1258300400004 DETECTOR (FISCH) Fission chamber. 1258300400005 ASSUMED (ASSUM1,95-AM-241(N,F),,SIG) 1258300400006 (ASSUM2,95-AM-242-M(N,F),,SIG) 1258300400007 DECAY-DATA (95-AM-242-G,16.HR,B-,,0.60) 1258300400008 Assumed 20% isomeric transition from 16-hr 242Am to 1258300400009 152-yr 242Am. 1258300400010 ENDBIB 8 0 1258300400011 COMMON 2 3 1258300400012 ASSUM1 ASSUM2 1258300400013 B B 1258300400014 33. 6000. 1258300400015 ENDCOMMON 3 0 1258300400016 DATA 2 1 1258300400017 EN-DUMMY DATA-APRX 1258300400018 MEV B 1258300400019 2.53 -08 2.000 +03 1258300400020 ENDDATA 3 0 1258300400021 ENDSUBENT 20 0 1258300499999 SUBENT 12583005 20080624 13491258300500001 BIB 5 7 1258300500002 REACTION (95-AM-242-M(N,F),,SIG,,SPA,DERIV) 1258300500003 INC-SPECT Thermal spectrum 1258300500004 DETECTOR (FISCH) Fission chamber. 1258300500005 ANALYSIS Obtained from authors absorption minus 1258300500006 capture. 1258300500007 STATUS (DEP,12583006) Obtained from author's absorption 1258300500008 (DEP,12583007) minus capture. 12583 5 8 1258300500009 ENDBIB 7 0 1258300500010 NOCOMMON 0 0 1258300500011 DATA 2 1 1258300500012 EN-DUMMY DATA-APRX 1258300500013 MEV B 1258300500014 2.53 -08 6.000 +03 1258300500015 ENDDATA 3 0 1258300500016 ENDSUBENT 15 0 1258300599999 SUBENT 12583006 20080624 13491258300600001 BIB 4 6 1258300600002 REACTION (95-AM-242-M(N,ABS),,SIG,,SPA) 1258300600003 INC-SPECT Reactor spectrum 1258300600004 METHOD (MASSP) Mass spectrometer 1258300600005 ANALYSIS Reanalysis of previously irradiated americium sample. 1258300600006 Principle uncertainties are in estimation of neutron 1258300600007 flux. 1258300600008 ENDBIB 6 0 1258300600009 NOCOMMON 0 0 1258300600010 DATA 2 1 1258300600011 EN-DUMMY DATA-APRX 1258300600012 MEV B 1258300600013 2.53 -08 8.000 +03 1258300600014 ENDDATA 3 0 1258300600015 ENDSUBENT 14 0 1258300699999 SUBENT 12583007 20080624 13491258300700001 BIB 4 6 1258300700002 REACTION (95-AM-242-M(N,G)95-AM-243,,SIG,,SPA) 1258300700003 INC-SPECT Reactor spectrum 1258300700004 METHOD (MASSP) Mass spectrometer 1258300700005 ANALYSIS Reanalysis of previously irradiated americium sample. 1258300700006 Principle uncertainties are in estimation of neutron 1258300700007 flux. 1258300700008 ENDBIB 6 0 1258300700009 NOCOMMON 0 0 1258300700010 DATA 2 1 1258300700011 EN-DUMMY DATA-APRX 1258300700012 MEV B 1258300700013 2.53 -08 2.000 +03 1258300700014 ENDDATA 3 0 1258300700015 ENDSUBENT 14 0 1258300799999 SUBENT 12583008 20080624 13491258300800001 BIB 2 2 1258300800002 REACTION (95-AM-243(N,F),,SIG,,MXW) 1258300800003 INC-SPECT Thermal spectrum 1258300800004 ENDBIB 2 0 1258300800005 NOCOMMON 0 0 1258300800006 DATA 2 1 1258300800007 EN-DUMMY DATA-MAX 1258300800008 MEV B 1258300800009 2.53 -08 4.0 +01 1258300800010 ENDDATA 3 0 1258300800011 ENDSUBENT 10 0 1258300899999 ENDENTRY 8 0 1258399999999