ENTRY 12248 20230413 150612248000 1 SUBENT 12248001 20230413 150612248001 1 BIB 9 30 12248001 2 TITLE Thermal neutron fission properties of Ra226 12248001 3 AUTHOR (D.Ames,A.Ghiorso) 12248001 4 REFERENCE (B,TRANSU.EL.,,1383,1949) 12248001 5 (R,ANL-4038,1947) 12248001 6 INSTITUTE (1USAANL) 12248001 7 FACILITY (REAC,1USAANL) Argonne heavy-water pile. 12248001 8 SAMPLE Radium used in early measurements was not purified 12248001 9 and taken directly as radium chloride. Spectrographic 12248001 10 analysis showed 0.4% of Ba, 0.2% of Ca, 0.04% of Mg, 12248001 11 and 0.02% of Si. The second sample was prepared from 12248001 12 20 mg of radium chloride that has been passed through 12248001 13 10 crystallization cycles. Spectrographic analysis 12248001 14 showed no significant impurities. 12248001 15 METHOD Two samples, each weighing 100 microg were evaporated 12248001 16 on platinum plates and tested for fission in the 12248001 17 thermal column of heavy-water pile. One had 43 12248001 18 fission per minute, and another one had 18 fission 12248001 19 per minute over the background of 100 fission per 12248001 20 minute. Comparison with fission standards indicated 12248001 21 cross sections of 2.6x10-4 and 1.1x10-4 b. The lowest 12248001 22 value was taken and assumed that that fission cross 12248001 23 section is no more than 1.1x10-4 b. 12248001 24 STATUS (TABLE,,D.Ames+,B,TRANSU.EL.,,1383,1949) 12248001 25 page 1384 of B,TRANSU.EL.,,1383,1949. 12248001 26 HISTORY (19760803T) Translated from SCISRS. 12248001 27 (19840821A) converted to reaction formalism 12248001 28 (20230413A) BP: Updated to new date formats, lower 12248001 29 case. Corrections according last EXFOR rules and Dict. 12248001 30 Corrected STATUS and book publication year, added 12248001 31 FACILITY, SAMPLE and METHOD. 12248001 32 ENDBIB 30 0 12248001 33 NOCOMMON 0 0 12248001 34 ENDSUBENT 33 0 1224800199999 SUBENT 12248002 20230413 150612248002 1 BIB 2 2 12248002 2 REACTION (88-RA-226(N,F),,SIG,,MXW) 12248002 3 INC-SPECT Thermal spectrum 12248002 4 ENDBIB 2 0 12248002 5 NOCOMMON 0 0 12248002 6 DATA 2 1 12248002 7 EN-DUMMY DATA-MAX 12248002 8 MEV B 12248002 9 2.53E-08 1.1E-04 12248002 10 ENDDATA 3 0 12248002 11 ENDSUBENT 10 0 1224800299999 ENDENTRY 2 0 1224899999999