ENTRY 31498 19990503 00003149800000001 SUBENT 31498001 19990503 00003149800100001 BIB 15 44 3149800100002 INSTITUTE (3BZLIEN) 3149800100003 REFERENCE (J,NSE,126,101,1997) 3149800100004 AUTHOR (J.CEZAR SUITA,A.GERBASI DA SILVA,L.TELMO AULER, 3149800100005 S.DE BARROS) 3149800100006 TITLE Neutron-Induced Reaction Cross Sections between 9 3149800100007 and 14 MeV 3149800100008 FACILITY (CYCLO,3BZLIEN) CV-28 cyclotron 3149800100009 INC-SOURCE (D-D ) 30 mm long 12 mm diameter cylindrical chamber 3149800100010 filled with 2 atm of deuterium gas was bombarded with 3149800100011 deutron beams of app. 2 mcA extracted from CV-28 3149800100012 cyclotron. Neutron flux was on the order of 10E+7 3149800100013 n/sec*cm2. 3149800100014 SAMPLE Natural nickel, cobalt and vanadium targets of 10 mm 3149800100015 diameter and 0.1 mm thickness, stacked with aluminium 3149800100016 foils of the same dimension, were placed 2 cm away 3149800100017 from the neutron source. Stacks were irradiated for 3149800100018 approximatly 5 h. 3149800100019 METHOD (ACTIV) Activity induced by the continous spectrum D-D 3149800100020 break up neutrons (0 - 6 MeV) was subtracted by an 3149800100021 unfolding technique using the aluminium monitor. 3149800100022 DETECTOR (GELI) Gamma ray activity was determined by high-purity3149800100023 detector shielded with 5 cm of lead with energy 3149800100024 resolution of 1.75 KeV at 1.33 MeV. 3149800100025 PART-DET (DG ) 3149800100026 MONITOR (13-AL-27(N,A)11-NA-24,,SIG) From ENDF/B-VI 3149800100027 DECAY-DATA Taken from U.Reus, W.Westmeir, 3149800100028 Atomic Data and Nuclear Data Table, Catalog of 3149800100029 Gamma Rays from Radioactive Decay, 3149800100030 Vol.29,No.1, Academic Press, New York, 1983. 3149800100031 STATUS Data from table 1 and 2 of Nuclear Science and 3149800100032 Engineering, vol.126(1997)101-107. 3149800100033 HISTORY (19990426C) VZ 3149800100034 ERR-ANALYS Data errors include uncertainty of: 3149800100035 deuteron beam energy 2% 3149800100036 gamma ray detector efficiency 3% 3149800100037 monitor reaction cross section 2% 3149800100038 cross section used in the determination of the 3149800100039 activity induced by the break up neutrons 3 to 4% 3149800100040 statistical error in the determination of the 3149800100041 gamma rays activity induced by monoenergetic and 3149800100042 break up neutrons 1 to 3% 3149800100043 contribution of break up neutrons to the activity 3149800100044 induced in the aluminium target at 13.3 and 13.8 MeV 3149800100045 were 0.7% and 2.7% respectively. 3149800100046 ENDBIB 44 0 3149800100047 NOCOMMON 0 0 3149800100048 ENDSUBENT 47 0 3149800199999 SUBENT 31498002 19990503 00003149800200001 BIB 2 5 3149800200002 REACTION (27-CO-59(N,P)26-FE-59,,SIG) 3149800200003 ERR-ANALYS Statistical error in the determination of the 3149800200004 gamma rays activity induced by monoenergetic and 3149800200005 break up neutrons for the 9.6 MeV measurement 3149800200006 was 32% 3149800200007 ENDBIB 5 0 3149800200008 NOCOMMON 0 0 3149800200009 DATA 4 2 3149800200010 EN EN-RSL DATA ERR-T 3149800200011 MEV MEV MB MB 3149800200012 9.6 0.2 55. 19. 3149800200013 13.3 0.2 61. 4. 3149800200014 ENDDATA 4 0 3149800200015 ENDSUBENT 14 0 3149800299999 SUBENT 31498003 19990503 00003149800300001 BIB 1 1 3149800300002 REACTION (27-CO-59(N,2N)27-CO-58,,SIG) 3149800300003 ENDBIB 1 0 3149800300004 NOCOMMON 0 0 3149800300005 DATA 4 2 3149800300006 EN EN-RSL DATA ERR-T 3149800300007 MEV MEV MB MB 3149800300008 12.4 0.2 290. 14. 3149800300009 13.3 0.2 489. 22. 3149800300010 ENDDATA 4 0 3149800300011 ENDSUBENT 10 0 3149800399999 SUBENT 31498004 19990503 00003149800400001 BIB 1 1 3149800400002 REACTION (23-V-51(N,A)21-SC-48,,SIG) 3149800400003 ENDBIB 1 0 3149800400004 NOCOMMON 0 0 3149800400005 DATA 4 2 3149800400006 EN EN-RSL DATA ERR-T 3149800400007 MEV MEV MB MB 3149800400008 12.4 0.2 10.2 0.5 3149800400009 13.3 0.2 11.5 0.5 3149800400010 ENDDATA 4 0 3149800400011 ENDSUBENT 10 0 3149800499999 SUBENT 31498005 19990503 00003149800500001 BIB 1 2 3149800500002 REACTION 1(28-NI-58(N,P)27-CO-58,,SIG) 3149800500003 2(28-NI-58(N,P)27-CO-58-M/G,,SIG/RAT) 3149800500004 ENDBIB 2 0 3149800500005 NOCOMMON 0 0 3149800500006 DATA 6 4 3149800500007 EN EN-RSL DATA 1ERR-T 1DATA 2ERR-T 23149800500008 MEV MEV MB MB NO-DIM NO-DIM 3149800500009 9.6 0.2 744. 40. 0.32 0.10 3149800500010 11.6 0.2 573. 44. 0.45 0.10 3149800500011 12.7 0.2 502. 70. 0.63 0.33 3149800500012 13.8 0.2 381. 90. 3149800500013 ENDDATA 6 0 3149800500014 ENDSUBENT 13 0 3149800599999 ENDENTRY 5 0 3149899999999