ENTRY 14050 20080710 13491405000000001 SUBENT 14050001 20080710 13491405000100001 BIB 8 11 1405000100002 INSTITUTE (1USAANL) 1405000100003 REFERENCE (J,NSE,2,33,1957) 1405000100004 (P,ANL-5322,,1954) 1405000100005 AUTHOR (G.L.Pyle,P.R.Fields,W.C.Bentley) 1405000100006 TITLE A study of the thermal neutron fissionability of 1405000100007 U239 and Th233 1405000100008 FACILITY (REAC,1USAANL) 1405000100009 INC-SOURCE (THCOL) Thermal neutron flux 1405000100010 DETECTOR (IOCH) Ionization chamber 1405000100011 HISTORY (20050928C) DR 1405000100012 (20080710A) BIB update 1405000100013 ENDBIB 11 0 1405000100014 COMMON 1 3 1405000100015 EN-DUMMY 1405000100016 EV 1405000100017 0.025 1405000100018 ENDCOMMON 3 0 1405000100019 ENDSUBENT 18 0 1405000199999 SUBENT 14050002 20080710 13491405000200001 BIB 5 7 1405000200002 REACTION (90-TH-233(N,F),,SIG,,MXW) 1405000200003 METHOD Natural thorium samples irradiated in MTR to form 1405000200004 233Th, then quickly inserted in thermal column where 1405000200005 fission rates were followed for several hours. 1405000200006 ERR-ANALYS No information 1405000200007 STATUS Data taken from text 1405000200008 HISTORY (20080710A) Reaction corrected. 1405000200009 ENDBIB 7 0 1405000200010 NOCOMMON 0 0 1405000200011 DATA 1 1 1405000200012 DATA-MAX 1405000200013 B 1405000200014 20. 1405000200015 ENDDATA 3 0 1405000200016 ENDSUBENT 15 0 1405000299999 SUBENT 14050003 20080710 13491405000300001 BIB 6 8 1405000300002 REACTION (92-U-239(N,F),,SIG,,MXW) 1405000300003 METHOD Depleted uranium samples irradiated in MTR to form 1405000300004 239U, then quickly inserted in thermal column where 1405000300005 fission rates were followed for several hours. 1405000300006 ASSUMED Value calculated assuming 239Pu(n,f) = 760 b. 1405000300007 ERR-ANALYS No information 1405000300008 STATUS Data taken from text 1405000300009 HISTORY (20080710A) Reaction and data corrected. 1405000300010 ENDBIB 8 0 1405000300011 NOCOMMON 0 0 1405000300012 DATA 1 1 1405000300013 DATA-MAX 1405000300014 B 1405000300015 20. 1405000300016 ENDDATA 3 0 1405000300017 ENDSUBENT 16 0 1405000399999 ENDENTRY 3 0 1405099999999