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