ENTRY 14655 20200425 14711465500000001 SUBENT 14655001 20200425 14711465500100001 BIB 8 12 1465500100002 TITLE Transplutonium Elements in Thermonuclear Test Debris 1465500100003 AUTHOR (P.R.Fields,M.H.Studier,H.Diamond,J.F.Mech, 1465500100004 M.G.Inghram,G.L.Pyle,C.M.Stevens,S.Fried,W.M.Manning, 1465500100005 A.Ghiorso,S.G.Thompson,G.H.Higgins,G.T.Seaborg) 1465500100006 REFERENCE (J,PR,102,180,1956) 1465500100007 #doi:10.1103/PhysRev.102.180 1465500100008 INSTITUTE (1USAANL,1USAUCX) 1465500100009 FACILITY (REAC,1USAANL) The Materials Testing Reactor (MTR). 1465500100010 ERR-ANALYS (DATA-ERR) No details on sources of uncertainties. 1465500100011 DECAY-DATA (96-CM-245,11500.YR,A) 1465500100012 (96-CM-246,4000.YR,A) 1465500100013 HISTORY (20200425C) BP 1465500100014 ENDBIB 12 0 1465500100015 NOCOMMON 0 0 1465500100016 ENDSUBENT 15 0 1465500199999 SUBENT 14655002 20200425 14711465500200001 BIB 6 22 1465500200002 REACTION (96-CM-245(N,F),,SIG,,SPA) 1465500200003 INC-SPECT Total flux 9x10**10 neutrons. 1465500200004 SAMPLE (96-CM-245,ENR=0.687) Sample I before irradiation. 1465500200005 (96-CM-246,ENR=0.284) Sample I before irradiation. 1465500200006 (96-CM-247,ENR=0.022) Sample I before irradiation. 1465500200007 (96-CM-248,ENR=0.007) Sample I before irradiation. 1465500200008 (96-CM-249,ENR=0.005) Sample I before irradiation. 1465500200009 (96-CM-245,ENR=0.207) Sample I after MTR irradiation. 1465500200010 (96-CM-246,ENR=0.751) Sample I after MTR irradiation. 1465500200011 (96-CM-247,ENR=0.042) Sample I after MTR irradiation. 1465500200012 METHOD (CHSEP,INTB) Sample was irradiated in the MTR for six 1465500200013 weeks and change in Cm245 contents was measured. 1465500200014 Alpha-pulse analysis of curium sample showed a rather 1465500200015 broad alpha peak with energy of about 5.4 MeV due to 1465500200016 Cm245 and Cm245. The ratios of the 5.4-MeV alpha 1465500200017 particles (Cm245 and Cm246) to spontaneous fission 1465500200018 disintegrations were (5.8+-0.3)x10**3 and (2.7+-0.1) 1465500200019 x10**3, respectively. 1465500200020 ANALYSIS A thermal-neutron fission cross section was 1465500200021 calculated for Cm245 based on the fissionability of a 1465500200022 sample I. 1465500200023 STATUS (TABLE) page 181. 1465500200024 ENDBIB 22 0 1465500200025 NOCOMMON 0 0 1465500200026 DATA 3 1 1465500200027 EN-DUMMY DATA DATA-ERR 1465500200028 EV B B 1465500200029 0.0253 1800.0 300.0 1465500200030 ENDDATA 3 0 1465500200031 ENDSUBENT 30 0 1465500299999 SUBENT 14655003 20200430 14711465500300001 BIB 6 24 1465500300002 REACTION (96-CM-245(N,F),,SIG,,SPA) 1465500300003 REL-REF (R,12585001,C.M.Stevens+,J,PR,94,974,1954) Previous 1465500300004 result. 1465500300005 SAMPLE Sample I, 4x10**21 neutrons. 1465500300006 Sample II, 8x10**21 neutrons. 1465500300007 (96-CM-242,ENR=0.168) Sample I 1465500300008 (96-CM-244,ENR=0.821) Sample I 1465500300009 (96-CM-245,ENR=0.0093) Sample I 1465500300010 (96-CM-246,ENR=0.0024) Sample I 1465500300011 (96-CM-242,ENR=0.0184) Sample II 1465500300012 (96-CM-244,ENR=0.9551) Sample II 1465500300013 (96-CM-245,ENR=0.0127) Sample II 1465500300014 (96-CM-246,ENR=0.0136) Sample II 1465500300015 (96-CM-247,ENR=0.00016) Sample II 1465500300016 METHOD (CHSEP,MASSP) The curium produced by the irradiation 1465500300017 of two plutonium samples (total integrated fluxes 1465500300018 4x10**21 and 8x10**21 neutrons) in the Materials 1465500300019 Testing Reactor (MTR) was chemically purified from 1465500300020 fission products and other actinide elements. The 1465500300021 curium samples were analyzed in a 12-in., 60 degree 1465500300022 mass spectrometer with a multiple filament source. 1465500300023 ANALYSIS Re-analysis of the previous measurement for fission 1465500300024 channel. 1465500300025 STATUS (TABLE) page 181. 1465500300026 ENDBIB 24 0 1465500300027 NOCOMMON 0 0 1465500300028 DATA 3 1 1465500300029 EN-DUMMY DATA DATA-ERR 1465500300030 EV B B 1465500300031 0.0253 2000.0 150.0 1465500300032 ENDDATA 3 0 1465500300033 ENDSUBENT 32 0 1465500399999 ENDENTRY 3 0 1465599999999