ENTRY 12249 20230413 1224900000001 SUBENT 12249001 20230413 20231011 1224900100001 BIB 9 19 1224900100002 TITLE Thermal neutron fission properties of Ac227, Ra223, 1224900100003 and Ra228 1224900100004 AUTHOR (S.Peterson,A.Ghiorso) 1224900100005 REFERENCE (B,TRANSU.EL.,,1381,1949) 1224900100006 (R,ANL-4039,1947) 1224900100007 INSTITUTE (1USAANL) 1224900100008 FACILITY (REAC,1USAANL) Argonne heavy-water pile. 1224900100009 STATUS (TABLE,,S.Peterson+,B,TRANSU.EL.,,1381,1949) 1224900100010 page 1382 of B,TRANSU.EL.,,1381,1949. 1224900100011 INC-SPECT Thermal spectrum. 1224900100012 METHOD Fission measurements were made in the thermal column 1224900100013 of heavy-pile with the high-sensitivity 1224900100014 fission-counting apparatus. 1224900100015 HISTORY (19760803T) Translated from SCISRS. 1224900100016 (19840821A) converted to reaction formalism 1224900100017 (20230413A) BP: Updated to new date formats, lower 1224900100018 case. Corrections according last EXFOR rules and 1224900100019 Dict. Corrected STATUS, TITLE and book publication 1224900100020 year, added FACILITY, SAMPLE and METHOD. 1224900100021 ENDBIB 19 0 1224900100022 NOCOMMON 0 0 1224900100023 ENDSUBENT 22 0 1224900199999 SUBENT 12249002 20230413 20231011 1224900200001 BIB 2 3 1224900200002 REACTION (88-RA-223(N,F),,SIG,,MXW) 1224900200003 SAMPLE A sample of 5x10-11 g of 223Ra showed no counts above 1224900200004 a background of 105 and 103 fission per minute. 1224900200005 ENDBIB 3 0 1224900200006 NOCOMMON 0 0 1224900200007 DATA 2 1 1224900200008 EN-DUMMY DATA-MAX 1224900200009 MEV B 1224900200010 2.53E-08 1.00E+02 1224900200011 ENDDATA 3 0 1224900200012 ENDSUBENT 11 0 1224900299999 SUBENT 12249003 20230413 20231011 1224900300001 BIB 2 3 1224900300002 REACTION (89-AC-227(N,F),,SIG,,MXW) 1224900300003 SAMPLE A single sample containing 10**-8 g of 227Ac was 1224900300004 tested for fission. 1224900300005 ENDBIB 3 0 1224900300006 NOCOMMON 0 0 1224900300007 DATA 2 1 1224900300008 EN-DUMMY DATA-MAX 1224900300009 MEV B 1224900300010 2.53E-08 2. 1224900300011 ENDDATA 3 0 1224900300012 ENDSUBENT 11 0 1224900399999 SUBENT 12249004 20230413 20231011 1224900400001 BIB 2 4 1224900400002 REACTION (88-RA-228(N,F),,SIG,,MXW) 1224900400003 SAMPLE A sample containing 4x10-9 g of 228Ra showed no 1224900400004 fission counts above a background for the counting 1224900400005 apparatus of 125 fission per minute. 1224900400006 ENDBIB 4 0 1224900400007 NOCOMMON 0 0 1224900400008 DATA 2 1 1224900400009 EN-DUMMY DATA-MAX 1224900400010 MEV B 1224900400011 2.53E-08 2. 1224900400012 ENDDATA 3 0 1224900400013 ENDSUBENT 12 0 1224900499999 ENDENTRY 4 0 1224999999999