ENTRY 10650 20080817 13491065000000001 SUBENT 10650001 20080817 13491065000100001 BIB 15 22 1065000100002 INSTITUTE (1USAORL) 1065000100003 REFERENCE (P,ORNL-4581,43,197009) 1065000100004 AUTHOR (C.E.Bemis Jr,R.E.Druschel,J.Halperin,R.D.Baybarz) 1065000100005 TITLE The neutron absorption cross section of 257Fm 1065000100006 FACILITY (REAC,1USAORL) ORR. 1065000100007 INC-SOURCE (REAC) Thermal neutrons from reactor 1065000100008 DETECTOR (SI) 1065000100009 PART-DET (A) Alpha particles detected from both irradiated and 1065000100010 unirradiated samples. 1065000100011 METHOD (CHSEP) Measured burnup of Fm relative to Cm in both 1065000100012 irradiated and unirradiated samples. 1065000100013 DECAY-DATA (100-FM-257,97.D,A,6519.,0.94) 1065000100014 MONITOR (96-CM-244(N,ABS),,SIG) 1065000100015 Flux measured with colbalt monitor. 1065000100016 DECAY-MON (96-CM-244,,A,5806.,0.764) 1065000100017 CORRECTION Corrected for sample decay. 1065000100018 STATUS No reply to author proof. 1065000100019 Data taken from text in reference. 1065000100020 HISTORY (19770307C) 1065000100021 (19831109A) Converted to REACTION formalism 1065000100022 (20080817A) Converted to new date formats, lower case. 1065000100023 BIB updates. 1065000100024 ENDBIB 22 0 1065000100025 NOCOMMON 0 0 1065000100026 ENDSUBENT 25 0 1065000199999 SUBENT 10650002 20080817 13491065000200001 BIB 3 3 1065000200002 REACTION (100-FM-257(N,ABS),,SIG,,SPA) 1065000200003 INC-SPECT Reactor spectrum 1065000200004 ERR-ANALYS (DATA-ERR) No information on source of uncertainty. 1065000200005 ENDBIB 3 0 1065000200006 NOCOMMON 0 0 1065000200007 DATA 3 1 1065000200008 EN-DUMMY DATA DATA-ERR 1065000200009 EV B B 1065000200010 0.0253 6100. 600. 1065000200011 ENDDATA 3 0 1065000200012 ENDSUBENT 11 0 1065000299999 SUBENT 10650003 20080620 13491065000300001 BIB 1 1 1065000300002 REACTION (100-FM-257(N,ABS),,RI) 1065000300003 ENDBIB 1 0 1065000300004 NOCOMMON 0 0 1065000300005 DATA 2 1 1065000300006 EN-MIN-APX DATA-MAX 1065000300007 EV B 1065000300008 0.5 5000. 1065000300009 ENDDATA 3 0 1065000300010 ENDSUBENT 9 0 1065000399999 SUBENT 10650004 20080817 13491065000400001 BIB 3 5 1065000400002 REACTION (100-FM-257(N,ABS),,SIG,,MXW) 1065000400003 ERR-ANALYS (DATA-ERR) No information on source of uncertainty. 1065000400004 STATUS (DEP,10650002) Determined from reactor spectrum 1065000400005 measurement of absorption cross section and resonance 1065000400006 integral. 1065000400007 ENDBIB 5 0 1065000400008 NOCOMMON 0 0 1065000400009 DATA 4 1 1065000400010 EN DATA-MIN DATA-MAX DATA-ERR 1065000400011 EV B B B 1065000400012 0.0253 5600. 6100. 600. 1065000400013 ENDDATA 3 0 1065000400014 ENDSUBENT 13 0 1065000499999 ENDENTRY 4 0 1065099999999