ENTRY 30439 20040714 00003043900000001 SUBENT 30439001 20040714 00003043900100001 BIB 13 24 3043900100002 INSTITUTE (3INDTRM) 3043900100003 REFERENCE (J,JIN,40,1981,197812) Final results 3043900100004 (P,BARC-900,91,1976) Preliminary results 3043900100005 AUTHOR (V.K.Bhargava, S.G.Marathe, V.K.Rao, S.M.Sahakundu, 3043900100006 R.Sampathkumar, N.K.Chaudhury, R.H.Iyer) 3043900100007 TITLE Absolute yields of 99Mo and 111Ag in the reactor 3043900100008 neutron induced fission of 238U 3043900100009 FACILITY (REAC) Apsara reactor 3043900100010 INC-SOURCE (REAC) 3043900100011 SAMPLE Purified depleted uranyl nitrate (containing 3043900100012 0.217% 235U) wrapped in 1 mm thick cadmium metal foil 3043900100013 METHOD (CHSEP) Radiochemical separations 3043900100014 DETECTOR (TRD) Solid state track detector for determination 3043900100015 of total number of fissions 3043900100016 (PROPC) Beta proportional counter 3043900100017 MONITOR Absolute 3043900100018 STATUS Data from J.Inorg.Nucl.Chem.40,1981(1978),table 1. 3043900100019 HISTORY (19790208C) OS. 3043900100020 (20040311U) SD: corrected 4-dig. year and lower cases. 3043900100021 ERR-ANALYS (DATA-ERR) Random experimental errors given including 3043900100022 uncertainties in track registration efficiency, 3043900100023 counting efficiencies, chemical yield determination and3043900100024 standardisation of carriers, statistical errors in 3043900100025 track counting 3043900100026 ENDBIB 24 0 3043900100027 COMMON 1 3 3043900100028 DATA-ERR 3043900100029 PER-CENT 3043900100030 5.0 3043900100031 ENDCOMMON 3 0 3043900100032 ENDSUBENT 31 0 3043900199999 SUBENT 30439002 19850121 00003043900200001 BIB 1 1 3043900200002 REACTION (92-U-238(N,F)ELEM/MASS,CUM,FY,,FIS) 3043900200003 ENDBIB 1 0 3043900200004 COMMON 1 3 3043900200005 EN-DUMMY 3043900200006 MEV 3043900200007 2.0000E+00 3043900200008 ENDCOMMON 3 0 3043900200009 DATA 4 2 3043900200010 ELEMENT MASS DATA DATA-ERR 3043900200011 NO-DIM NO-DIM PC/FIS PC/FIS 3043900200012 4.2000E+01 9.9000E+01 6.2700E+00 3.0000E-01 3043900200013 4.7000E+01 1.1100E+02 4.6000E-02 2.0000E-03 3043900200014 ENDDATA 4 0 3043900200015 ENDSUBENT 14 0 3043900299999 ENDENTRY 2 0 3043999999999