ENTRY 12509 19830809 00001250900000001 SUBENT 12509001 19830809 00001250900100001 BIB 8 10 1250900100002 INSTITUTE (1USAORL) 1250900100003 REFERENCE (P,ORNL-2081,102,5611) 1250900100004 AUTHOR (W.W.PRATT,F.J.MUCKENTHALER,E.G.SLIVER) 1250900100005 TITLE THERMAL-NEUTRON FISSION CROSS SECTION OF PU239 AND 1250900100006 PU240. 1250900100007 N-SOURCE (REAC) U-GRAPHITE REACTOR, X-10. 1250900100008 INC-SPECT NEUTRON TEMPERATURE ESTIMATED TO BE 495 DEGR(K). 1250900100009 STATUS (SCSRS) 1250900100010 HISTORY (760804T) TRANSLATED FROM SCISRS 1250900100011 (830809A) CONVERTED TO REACTION FORMALISM 1250900100012 ENDBIB 10 0 1250900100013 NOCOMMON 0 0 1250900100014 ENDSUBENT 13 0 1250900199999 SUBENT 12509002 19830809 00001250900200001 BIB 4 5 1250900200002 REACTION (94-PU-239(N,F),,SIG) 1250900200003 STATUS (DEP) FROM MEASURED RATIO TO U-235 1250900200004 DETECTOR (FISCH) BACK-TO-BACK FISSION COUNTER 1250900200005 MONITOR (92-U-235(N,F),,SIG) 1250900200006 BASED ON U235 THERMAL FISSION=580B. 1250900200007 ENDBIB 5 0 1250900200008 NOCOMMON 0 0 1250900200009 DATA 4 1 1250900200010 EN DATA DATA-ERR MONIT 1250900200011 EV B B B 1250900200012 0.0253 715. 15. 580. 1250900200013 ENDDATA 3 0 1250900200014 ENDSUBENT 13 0 1250900299999 SUBENT 12509003 19830809 00001250900300001 BIB 1 2 1250900300002 REACTION ((94-PU-239(N,F),,SIG,,MXW)/ 1250900300003 (92-U-235(N,F),,SIG,,MXW)) 1250900300004 ENDBIB 2 0 1250900300005 NOCOMMON 0 0 1250900300006 DATA 3 1 1250900300007 EN-DUMMY DATA DATA-ERR 1250900300008 MEV NO-DIM NO-DIM 1250900300009 2.53 -08 1.725 +00 2.7 -02 1250900300010 ENDDATA 3 0 1250900300011 ENDSUBENT 10 0 1250900399999 SUBENT 12509004 19830809 00001250900400001 BIB 4 4 1250900400002 REACTION (94-PU-240(N,F),,SIG) 1250900400003 STATUS (DEP,12509005) 1250900400004 DETECTOR (FISCH) BACK-TO-BACK FISSION COUNTER 1250900400005 MONITOR (92-U-235(N,F),,SIG) 1250900400006 ENDBIB 4 0 1250900400007 NOCOMMON 0 0 1250900400008 DATA 3 1 1250900400009 EN DATA DATA-ERR 1250900400010 MEV B B 1250900400011 2.53 -08 3.7 +00 8.0 +00 1250900400012 ENDDATA 3 0 1250900400013 ENDSUBENT 12 0 1250900499999 SUBENT 12509005 19830809 00001250900500001 BIB 2 3 1250900500002 REACTION ((94-PU-240(N,F),,SIG,,MXW)/ 1250900500003 (92-U-235(N,F),,SIG,,MXW)) 1250900500004 INC-SPECT THERMAL SPECTRUM 1250900500005 ENDBIB 3 0 1250900500006 NOCOMMON 0 0 1250900500007 DATA 3 1 1250900500008 EN-DUMMY DATA DATA-ERR 1250900500009 MEV NO-DIM NO-DIM 1250900500010 2.53 -08 7.0 -03 1.54 -02 1250900500011 ENDDATA 3 0 1250900500012 ENDSUBENT 11 0 1250900599999 ENDENTRY 5 0 1250999999999