ENTRY 13583 19930330 00001358300000001 SUBENT 13583001 19930330 00001358300100001 BIB 11 15 1358300100002 INSTITUTE (1USALRL) 1358300100003 REFERENCE (J,PR,99,183,5507) 1358300100004 AUTHOR (G.H.HIGGINS,W.W.T.CRANE,S.R.GUNN) 1358300100005 TITLE Average Number of Neutrons per Spontaneous Fission of 1358300100006 Cm244 1358300100007 SAMPLE Sample contains unspecified amount of 242Cm. 1358300100008 DETECTOR (SCIN) Large tank containg a saturated solution of 1358300100009 manganese sulphate. 1358300100010 DECAY-DATA Alpha decay energies and half-lives taken from 1358300100011 Hollander, et al., Rev.Mod.Phys. 25, 469 (1953). 1358300100012 CORRECTION Corrected for neutrons from spontaneous fission of 1358300100013 242Cm in sample using nu(bar)=3.0+-0.3. 1358300100014 ERR-ANALYS (DATA-ERR) No information on source of error given. 1358300100015 STATUS Data taken from article 1358300100016 HISTORY (930330C) 1358300100017 ENDBIB 15 0 1358300100018 NOCOMMON 0 0 1358300100019 ENDSUBENT 18 0 1358300199999 SUBENT 13583002 19930330 00001358300200001 BIB 1 1 1358300200002 REACTION (96-CM-244(0,F),,NU) 1358300200003 ENDBIB 1 0 1358300200004 NOCOMMON 0 0 1358300200005 DATA 2 1 1358300200006 DATA DATA-ERR 1358300200007 NO-DIM NO-DIM 1358300200008 2.60 0.11 1358300200009 ENDDATA 3 0 1358300200010 ENDSUBENT 9 0 1358300299999 ENDENTRY 2 0 1358399999999