ENTRY 31600 20100317 31453160000000001 SUBENT 31600001 20100317 31453160000100001 BIB 14 50 3160000100002 TITLE Measurement of cross sections for the reactions 3160000100003 665Cu(n,alpha)62gCo, 65Cu(n,p)65Ni, 65Cu(n,2n)64Cu, 3160000100004 58Ni(n,2n)57Ni and 58N(n,p)58m+gCo at 14.8 MeV 3160000100005 neutron energy 3160000100006 AUTHOR (A.K.M.Harun-Ar-Rashid,M.U.Khandaker,M.N.Islam, 3160000100007 A.K.M.M.H.Meaze,Sk.A.Latif,M.A.Halim,K.Naher, 3160000100008 M.N.Chowdhury,M.S.Uddin,M.A.Hafiz,M.M.Rahman) 3160000100009 INSTITUTE (3BANSAV) 3160000100010 (3BANBAN) Chittagong University, Chittagong 4331, 3160000100011 Bangladesh 3160000100012 REFERENCE (J,IJP,80,737,2006) 3160000100013 FACILITY (CCW,3BANSAV) J-25 (AID,PRANCE) neutron generator 3160000100014 The main operational parameters of the neutron 3160000100015 generator were the following: 3160000100016 * High voltage -110 KV, 3160000100017 * Beam curent - 100 microA, 3160000100018 * Beam diameter-0.5 cm. 3160000100019 SAMPLE Square shaped (1 cm x 1 cm) high purity nickel (> 99%) 3160000100020 and copper ( > 99.99%) foils (0.044 g and 0.0936 g, 3160000100021 respectively) of natural isotopic abundance were 3160000100022 prepared very precisely. The nickel and copper foils 3160000100023 were sealed in thin polythene bags and sandwiched 3160000100024 between three layers of aluminum flux monitor foils 3160000100025 in the following order : (Al1 + Ni + Al2 + Cu + Al3). 3160000100026 INC-SOURCE (D-T) 3H(d,n)4He reaction 3160000100027 METHOD (ACTIV) Activation method. 3160000100028 (STATD) Each cross section value is based on two or 3160000100029 three independent measurements. 3160000100030 MONITOR (13-AL-27(N,A)11-NA-24,,SIG) 3160000100031 MONIT-REF (,,R,IAEA-227,59,1983) 3160000100032 DECAY-MON (11-NA-24,15.02HR,DG,1369.,1.0) 3160000100033 ERR-ANALYS (ERR-T) Total error is given. 3160000100034 The partial uncertainties from: 3160000100035 (ERR-7,0.3,1.) decay data - 0.3 to 1% 3160000100036 (ERR-8,0.3,1.) gamma-ray emission 3160000100037 probability - 0.3 to 1% 3160000100038 (ERR-9,1.,1.5) error in peak area 3160000100039 analysis - 1.0 to 1.5% 3160000100040 - statistical uncertainty and: 3160000100041 (ERR-1) efficiency of detector - 2% 3160000100042 (ERR-2) neutron absorption and scattering - 0.5% 3160000100043 (ERR-3) self-absorption of gamma rays in sample - 0.5% 3160000100044 (ERR-4) neutron flux variation with time - 1.% 3160000100045 (ERR-5) sample weight - less than 1.0% 3160000100046 (ERR-6) error in absolute neutron flux determinat.- 3% 3160000100047 STATUS (TABLE) Data taken from Table 2 of main reference. 3160000100048 HISTORY (20070727C) SD 3160000100049 (20080125U) SD. TITLE corrected. A few misprints. 3160000100050 (20100317U) SD: Author's list was corrected: 3160000100051 additional spaces were deleted. 3160000100052 ENDBIB 50 0 3160000100053 COMMON 6 3 3160000100054 ERR-1 ERR-2 ERR-3 ERR-4 ERR-5 ERR-6 3160000100055 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 3160000100056 2.0 0.5 0.5 1.0 1.0 3.0 3160000100057 ENDCOMMON 3 0 3160000100058 ENDSUBENT 57 0 3160000199999 SUBENT 31600002 20070727 31233160000200001 BIB 2 2 3160000200002 REACTION (28-NI-58(N,2N)28-NI-57,,SIG) 3160000200003 DECAY-DATA (28-NI-57,36.HR,DG,1377.6,0.849) 3160000200004 ENDBIB 2 0 3160000200005 NOCOMMON 0 0 3160000200006 DATA 3 1 3160000200007 EN DATA ERR-T 3160000200008 MEV MB MB 3160000200009 14.8 23.75 2.84 3160000200010 ENDDATA 3 0 3160000200011 ENDSUBENT 10 0 3160000299999 SUBENT 31600003 20070727 31233160000300001 BIB 2 2 3160000300002 REACTION (28-NI-58(N,P)27-CO-58,,SIG) 3160000300003 DECAY-DATA (27-CO-58,70.78D,DG,810.6,0.994) 3160000300004 ENDBIB 2 0 3160000300005 NOCOMMON 0 0 3160000300006 DATA 3 1 3160000300007 EN DATA ERR-T 3160000300008 MEV MB MB 3160000300009 14.8 384.27 33.12 3160000300010 ENDDATA 3 0 3160000300011 ENDSUBENT 10 0 3160000399999 SUBENT 31600004 20070727 31233160000400001 BIB 2 2 3160000400002 REACTION (29-CU-65(N,A)27-CO-62-M,,SIG) 3160000400003 DECAY-DATA (27-CO-62-M,13.9MIN,DG,1172.,0.99) 3160000400004 ENDBIB 2 0 3160000400005 NOCOMMON 0 0 3160000400006 DATA 3 1 3160000400007 EN DATA ERR-T 3160000400008 MEV MB MB 3160000400009 14.8 8.89 1.27 3160000400010 ENDDATA 3 0 3160000400011 ENDSUBENT 10 0 3160000499999 SUBENT 31600005 20070727 31233160000500001 BIB 2 2 3160000500002 REACTION (29-CU-65(N,P)28-NI-65,,SIG) 3160000500003 DECAY-DATA (28-NI-65,2.52HR,DG,1115.5,0.152) 3160000500004 ENDBIB 2 0 3160000500005 NOCOMMON 0 0 3160000500006 DATA 3 1 3160000500007 EN DATA ERR-T 3160000500008 MEV MB MB 3160000500009 14.8 18.83 1.70 3160000500010 ENDDATA 3 0 3160000500011 ENDSUBENT 10 0 3160000599999 SUBENT 31600006 20070727 31233160000600001 BIB 2 2 3160000600002 REACTION (29-CU-65(N,2N)29-CU-64,,SIG) 3160000600003 DECAY-DATA (29-CU-64,12.74HR,DG,511.,0.37) 3160000600004 ENDBIB 2 0 3160000600005 NOCOMMON 0 0 3160000600006 DATA 3 1 3160000600007 EN DATA ERR-T 3160000600008 MEV MB MB 3160000600009 14.8 850.41 103.66 3160000600010 ENDDATA 3 0 3160000600011 ENDSUBENT 10 0 3160000699999 ENDENTRY 6 0 3160099999999