ENTRY 13434 20240213 1343400000001 SUBENT 13434001 20240213 20240513 1343400100001 BIB 8 12 1343400100002 INSTITUTE (1CANCRC) 1343400100003 REFERENCE (J,JIN,5,93,1957) 1343400100004 #doi:10.1016/0022-1902(57)80049-9 1343400100005 AUTHOR (W.E.Grummitt,G.M.Milton) 1343400100006 TITLE The independent yields of 140La, 90Y, and 91Y in the 1343400100007 thermal neutron fission of 235U and 233U 1343400100008 FACILITY (REAC,1CANCRC) NRX 1343400100009 METHOD (CHSEP) 1343400100010 ERR-ANALYS (DATA-ERR) No details on sources of uncertainties 1343400100011 HISTORY (19891214C) VM 1343400100012 (20240211A) OS. REACTIONs corrected, STATUS updated, 1343400100013 ERR-ANALYS added, converted to lower and upper case 1343400100014 ENDBIB 12 0 1343400100015 COMMON 1 3 1343400100016 EN-DUMMY 1343400100017 EV 1343400100018 0.0253 1343400100019 ENDCOMMON 3 0 1343400100020 ENDSUBENT 19 0 1343400199999 SUBENT 13434002 20240213 20240513 1343400200001 BIB 4 5 1343400200002 REACTION (92-U-233(N,F)ELEM/MASS,IND,FY,,FRC/SPA) 1343400200003 SAMPLE 233U in solution as uranyl nitrate 1343400200004 STATUS (TABLE,,W.E.Grummitt+,J,JIN,5,93,1957) Tables 1+2 1343400200005 HISTORY (20240211A) REACTION modified (reaction combination 1343400200006 -> SF8=FRC) 1343400200007 ENDBIB 5 0 1343400200008 NOCOMMON 0 0 1343400200009 DATA 5 2 1343400200010 ELEMENT MASS DATA DATA-ERR DATA-MAX 1343400200011 NO-DIM NO-DIM NO-DIM NO-DIM NO-DIM 1343400200012 39. 90. 8.0 -05 1343400200013 57. 140. 3.8 -03 0.1 -03 1343400200014 ENDDATA 4 0 1343400200015 ENDSUBENT 14 0 1343400299999 SUBENT 13434003 20240213 20240513 1343400300001 BIB 4 5 1343400300002 REACTION (92-U-235(N,F)ELEM/MASS,IND,FY,,FRC/SPA) 1343400300003 SAMPLE Natural U(3)O(8) 1343400300004 STATUS (TABLE,,W.E.Grummitt+,J,JIN,5,93,1957) Tables 1+2 1343400300005 HISTORY (20240211A) REACTION modified (reaction combination 1343400300006 -> SF8=FRC) 1343400300007 ENDBIB 5 0 1343400300008 NOCOMMON 0 0 1343400300009 DATA 4 1 1343400300010 ELEMENT MASS DATA DATA-ERR 1343400300011 NO-DIM NO-DIM NO-DIM NO-DIM 1343400300012 57. 140. 7.0 -04 0.4 -04 1343400300013 ENDDATA 3 0 1343400300014 ENDSUBENT 13 0 1343400399999 ENDENTRY 3 0 1343499999999