ENTRY 11929 19830802 00001192900000001 SUBENT 11929001 19830802 00001192900100001 BIB 10 13 1192900100002 INSTITUTE (1USAORL) 1192900100003 REFERENCE (P,ORNL-3679,11,64) 1192900100004 AUTHOR (P.LANTZ) 1192900100005 TITLE THERMAL-NEUTRON CROSS SECTION AND RESONANCE INTEGRAL OF1192900100006 RU104. 1192900100007 INC-SPECT REACTOR SPECTRUM 1192900100008 MONITOR (27-CO-59(N,G)27-CO-60,,SIG) 1192900100009 (79-AU-197(N,G)79-AU-198,,SIG) 1192900100010 METHOD (ACTIV) ACTIVATION 1192900100011 DECAY-DATA (44-RU-105,4.5HR,DG,726.) 1192900100012 STATUS (SCSRS) 1192900100013 HISTORY (760802T) TRANSLATED FROM SCISRS 1192900100014 (830802A) CONVERTED TO REACTION FORMALISM 1192900100015 ENDBIB 13 0 1192900100016 NOCOMMON 0 0 1192900100017 ENDSUBENT 16 0 1192900199999 SUBENT 11929002 19830802 00001192900200001 BIB 2 3 1192900200002 REACTION (44-RU-104(N,G)44-RU-105,,SIG,,MXW) 1192900200003 ANALYSIS AVERAGE OF 4 VALUES CALCULATED FROM MEASUREMENT IN 1192900200004 REACTOR SPECTRUM. 1192900200005 ENDBIB 3 0 1192900200006 NOCOMMON 0 0 1192900200007 DATA 2 1 1192900200008 EN-DUMMY DATA 1192900200009 MEV B 1192900200010 2.53 -08 4.8 -01 1192900200011 ENDDATA 3 0 1192900200012 ENDSUBENT 11 0 1192900299999 SUBENT 11929003 19830802 00001192900300001 BIB 2 2 1192900300002 REACTION (44-RU-104(N,G)44-RU-105,,SIG) 1192900300003 STATUS (DEP,11929002) 1192900300004 ENDBIB 2 0 1192900300005 NOCOMMON 0 0 1192900300006 DATA 2 1 1192900300007 EN DATA 1192900300008 MEV B 1192900300009 2.53 -08 4.7 -01 1192900300010 ENDDATA 3 0 1192900300011 ENDSUBENT 10 0 1192900399999 SUBENT 11929004 19830802 00001192900400001 BIB 1 1 1192900400002 REACTION (44-RU-104(N,G)44-RU-105,,RI) 1192900400003 ENDBIB 1 0 1192900400004 NOCOMMON 0 0 1192900400005 DATA 2 1 1192900400006 EN-MIN DATA 1192900400007 MEV B 1192900400008 5. -07 4.6 +00 1192900400009 ENDDATA 3 0 1192900400010 ENDSUBENT 9 0 1192900499999 ENDENTRY 4 0 1192999999999