ENTRY 12248 20230413 1224800000001 SUBENT 12248001 20230413 20231011 1224800100001 BIB 9 30 1224800100002 TITLE Thermal neutron fission properties of Ra226 1224800100003 AUTHOR (D.Ames,A.Ghiorso) 1224800100004 REFERENCE (B,TRANSU.EL.,,1383,1949) 1224800100005 (R,ANL-4038,1947) 1224800100006 INSTITUTE (1USAANL) 1224800100007 FACILITY (REAC,1USAANL) Argonne heavy-water pile. 1224800100008 SAMPLE Radium used in early measurements was not purified 1224800100009 and taken directly as radium chloride. Spectrographic 1224800100010 analysis showed 0.4% of Ba, 0.2% of Ca, 0.04% of Mg, 1224800100011 and 0.02% of Si. The second sample was prepared from 1224800100012 20 mg of radium chloride that has been passed through 1224800100013 10 crystallization cycles. Spectrographic analysis 1224800100014 showed no significant impurities. 1224800100015 METHOD Two samples, each weighing 100 microg were evaporated 1224800100016 on platinum plates and tested for fission in the 1224800100017 thermal column of heavy-water pile. One had 43 1224800100018 fission per minute, and another one had 18 fission 1224800100019 per minute over the background of 100 fission per 1224800100020 minute. Comparison with fission standards indicated 1224800100021 cross sections of 2.6x10-4 and 1.1x10-4 b. The lowest 1224800100022 value was taken and assumed that that fission cross 1224800100023 section is no more than 1.1x10-4 b. 1224800100024 STATUS (TABLE,,D.Ames+,B,TRANSU.EL.,,1383,1949) 1224800100025 page 1384 of B,TRANSU.EL.,,1383,1949. 1224800100026 HISTORY (19760803T) Translated from SCISRS. 1224800100027 (19840821A) converted to reaction formalism 1224800100028 (20230413A) BP: Updated to new date formats, lower 1224800100029 case. Corrections according last EXFOR rules and Dict. 1224800100030 Corrected STATUS and book publication year, added 1224800100031 FACILITY, SAMPLE and METHOD. 1224800100032 ENDBIB 30 0 1224800100033 NOCOMMON 0 0 1224800100034 ENDSUBENT 33 0 1224800199999 SUBENT 12248002 20230413 20231011 1224800200001 BIB 2 2 1224800200002 REACTION (88-RA-226(N,F),,SIG,,MXW) 1224800200003 INC-SPECT Thermal spectrum 1224800200004 ENDBIB 2 0 1224800200005 NOCOMMON 0 0 1224800200006 DATA 2 1 1224800200007 EN-DUMMY DATA-MAX 1224800200008 MEV B 1224800200009 2.53E-08 1.1E-04 1224800200010 ENDDATA 3 0 1224800200011 ENDSUBENT 10 0 1224800299999 ENDENTRY 2 0 1224899999999