ENTRY 12975 19861006 00001297500000001 SUBENT 12975001 19861006 00001297500100001 BIB 15 25 1297500100002 INSTITUTE (1USAANL) 1297500100003 REFERENCE (C,85SANTA,1,163,8505) 1297500100004 (P,DOE-NDC-36,3,8504) 1297500100005 (P,DOE-ER-0046/17,11,8405) 1297500100006 AUTHOR (L.R.GREENWOOD,R.K.SMITHER) 1297500100007 TITLE NEW NEUTRON CROSS SECTIONS FOR FUSION MATERIALS STUDIES1297500100008 FACILITY (CCW,1USAPTN) PLASMA PHYSICS LABORATORY NEUTRON 1297500100009 GENERATOR 1297500100010 METHOD (ACTIV) 1297500100011 INC-SOURCE (D-T) 1297500100012 MONITOR (13-AL-27(N,P)12-MG-27,,SIG) ENDF/B-V DOSIMETRY FILE 1297500100013 (13-AL-27(N,A)11-NA-24,,SIG) 1297500100014 DECAY-MON (12-MG-27,9.54MIN,DG,844.) 1297500100015 (11-NA-24,15.HR,DG,1369.) 1297500100016 DETECTOR (GELI) 1297500100017 SAMPLE ENRICHED IRON SAMPLE 97. PERCENT 54-FE 1297500100018 2.57 PERCENT 56-FE 1297500100019 CORRECTION DATA ARE CORRECTED FOR GAMMA ABSORPTION AND DECAY 1297500100020 DURING AND AFTER IRRADIATION 1297500100021 ERR-ANALYS (DATA-ERR) RELATIVE ERROR 1297500100022 NORMALIZATION ERROR APROXIMATELY 12 PERCENT 1297500100023 STATUS DATA RECIEVED IN PRIVATE COMMUNICATION 86/9/22 FROM 1297500100024 L. R. GREENWOOD 1297500100025 (APRVD) L.R.GREENWOOD, 86/10/16 1297500100026 HISTORY (861001C) 1297500100027 ENDBIB 25 0 1297500100028 COMMON 1 3 1297500100029 EN-RSL 1297500100030 KEV 1297500100031 200. 1297500100032 ENDCOMMON 3 0 1297500100033 ENDSUBENT 32 0 1297500199999 SUBENT 12975002 19861006 00001297500200001 BIB 2 2 1297500200002 REACTION (26-FE-54(N,2N)26-FE-53,,SIG) 1297500200003 DECAY-DATA (26-FE-53-G,8.53MIN,DG,378.,.4) 1297500200004 ENDBIB 2 0 1297500200005 NOCOMMON 0 0 1297500200006 DATA 3 6 1297500200007 EN DATA DATA-ERR 1297500200008 MEV MB PER-CENT 1297500200009 13.95 0.68 14. 1297500200010 14.01 0.80 18. 1297500200011 14.31 2.55 6. 1297500200012 14.46 3.70 3. 1297500200013 14.61 5.05 6. 1297500200014 14.64 5.85 3. 1297500200015 ENDDATA 8 0 1297500200016 ENDSUBENT 15 0 1297500299999 ENDENTRY 2 0 1297599999999