ENTRY 23270 20151210 22482327000000001 SUBENT 23270001 20151210 22482327000100001 BIB 18 69 2327000100002 TITLE 65Cu isomeric cross section for (n,alpha) reaction 2327000100003 using approximately 14 MeV neutrons . 2327000100004 AUTHOR (A.Durusoy,I.A.Reyhancan,Oe.Akcali) 2327000100005 INSTITUTE (2TUKYTU) A.Durusoy, Oe.Akcali 2327000100006 (2TUKSTU) I.A.Reyhancan 2327000100007 REFERENCE (J,ARI,99,86,2015) Data tables. 2327000100008 #doi:10.1016/j.apradiso.2015.02.013 2327000100009 REL-REF (I,,M.Subasi+,J,NSE,135,260,2000) 2327000100010 (R,21807001,A.Pavlik+,J,JP/G,8,1283,1982) 2327000100011 90Zr(n,2n)89Zr c-s data used in ZR/Nb method. 2327000100012 (R,10709001,D.R.Nethaway,J,JIN,40,1285,1978) 2327000100013 93Nb(n,2n)92mNb c-s data used in ZR/Nb method 2327000100014 (M,,V.E.Lewis+,J,NIM,174,141,1980) 2327000100015 Zr/Nb ratio method . 2327000100016 (M,22474001,M.Subasi+,J,NSE,122,(1),423,1996) 2327000100017 Details of Zr/Nb method. Gamma counting system. 2327000100018 (R,,R.B.Firestone+,B,FIRESTONE,,1998) CD-ROM Edition. 2327000100019 Decay data are form ref.of R.Firestone+ and 2327000100020 J.K.Tuli,Nuclear Wallet Cards, 6th Edition, 2000. 2327000100021 FACILITY (LINAC,2TUKCNA) SAMES T-400 Neutron Generator in 2327000100022 combination with a Fast Sample Transfer System (FSTS), 2327000100023 which can transfer the sample from the irradiation 2327000100024 position to HpGe detector or vice versa within 0.5 s. 2327000100025 SAMPLE Cu samples of ~4.6886g, 99.9% purity, packed in thin 2327000100026 polyethylene boxes of 13mm diameter, 8.5mm height. 2327000100027 Al sample of 2327000100028 INC-SOURCE (D-T) H-3(D,N)He-4 reaction . Deuteron beam current 2327000100029 200 microA, accelerating voltage 250 kV. 2327000100030 INC-SPECT At the irradiation place (70 mm from neutron source), 2327000100031 neutron fluxes were from 1.E+7 to 6.E+7 n/cm2/s, 2327000100032 depending on the neutron target condition. 2327000100033 METHOD (ACTIV) 2327000100034 The angles of irradiation positions 0, 30, 60, 90, 120,2327000100035 130 deg ( relative to deuteron beam) correspond to 2327000100036 14.86, 14.72, 14.46, 14.10, 13.68, 13.60 MeV neutron 2327000100037 energies, respectively. 2327000100038 DETECTOR (HPGE) HPGe detector to measure 843.4 keV gamma 2327000100039 activity of Al sample. 2327000100040 (SCIN) NE102A scintillation detector for neutron flux 2327000100041 monitoring, placed at 104 cm distance from sample. 2327000100042 MONITOR (13-AL-27(N,P)12-MG-27,,SIG) 2327000100043 DECAY-MON (12-MG-27,9.458MIN,DG,843.8,0.73) 2327000100044 Neutron flux monitoring. 2327000100045 MONIT-REF (,,3,ENDF/B-VII.1,,2011) 2327000100046 ANALYSIS Cyclic activation formula was used. 2327000100047 CORRECTION Self-absorption corrections . 2327000100048 Attenuation of the gamma rays in a beta absorber. 2327000100049 Dead time. 2327000100050 Low-energy-neutron contribution- ~7 %. 2327000100051 ERR-ANALYS (ERR-T) Total error 8.0% . 2327000100052 Sources of uncertainties: 2327000100053 (ERR-1) Sample weight . 2327000100054 (ERR-2) Concentration of the element. 2327000100055 (ERR-3) Relative gamma ray intensity. 2327000100056 (ERR-4) Isotopic abundance . 2327000100057 (ERR-5) Solid angle and intrinsic efficiency of the 2327000100058 gamma detector . 2327000100059 (ERR-S) Statistical error of the gamma-ray photo-peak 2327000100060 area . 2327000100061 (ERR-6) Neutron flux fluctuation . 2327000100062 (ERR-7) Effective neutron flux ( including reference 2327000100063 cross section) . 2327000100064 (ERR-8) Irradiation, cooling and measuring times. 2327000100065 (ERR-9) Coincidence summing . 2327000100066 The uncertainties were assumed to be uncorrelated, 2327000100067 the total uncertainties could be determined by adding 2327000100068 the experimental errors and the uncertainties of 2327000100069 nuclear data in quadratic form 2327000100070 HISTORY (20131010C) M.M. 2327000100071 ENDBIB 69 0 2327000100072 COMMON 10 6 2327000100073 ERR-1 ERR-2 ERR-3 ERR-4 ERR-5 ERR-6 2327000100074 ERR-7 ERR-8 ERR-9 ERR-S 2327000100075 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2327000100076 PER-CENT PER-CENT PER-CENT PER-CENT 2327000100077 0.1 0.5 0.2 0.1 3.0 1.0 2327000100078 3.0 0.1 3.0 6.0 2327000100079 ENDCOMMON 6 0 2327000100080 ENDSUBENT 79 0 2327000199999 SUBENT 23270002 20151210 22482327000200001 BIB 6 11 2327000200002 REACTION (29-CU-65(N,A)27-CO-62-M,,SIG) 2327000200003 DECAY-DATA (27-CO-62-M,13.86MIN,DG,1163.5,0.705) 2327000200004 SAMPLE (29-CU-65,NAT=0.3083) 2327000200005 Isotopic abundance (30.83+-0.15) % . 2327000200006 ADD-RES (COMP) Theoretical calculations by Talys 1.6 . 2327000200007 ERR-ANALYS (ERR-HL) Error of half-life given in DECAY-DATA . 2327000200008 (ERR-IDD) Error of intensity given in DECAY-DATA 2327000200009 (ERR-EDD) Error of energy given in DECAY-DATA . 2327000200010 STATUS (TABLE) Tables: 1 - monitor, 2 - decay data, 2327000200011 3 - uncertainties, 4 - cross sections 2327000200012 in ARI,99,86,2015 . 2327000200013 ENDBIB 11 0 2327000200014 COMMON 3 3 2327000200015 ERR-HL ERR-IDD ERR-EDD 2327000200016 MIN NO-DIM KEV 2327000200017 0.09 0.002 0.1 2327000200018 ENDCOMMON 3 0 2327000200019 DATA 6 6 2327000200020 EN EN-ERR DATA ERR-T MONIT MONIT-ERR 2327000200021 MEV MEV MB MB MB MB 2327000200022 13.60 0.04 7.60 0.61 76.10 2.28 2327000200023 13.68 0.04 6.56 0.53 73.83 2.22 2327000200024 14.10 0.05 7.76 0.62 70.67 2.12 2327000200025 14.46 0.06 8.75 0.70 67.92 2.04 2327000200026 14.72 0.06 7.97 0.64 64.61 1.94 2327000200027 14.86 0.08 8.11 0.65 61.91 1.86 2327000200028 ENDDATA 8 0 2327000200029 ENDSUBENT 28 0 2327000299999 ENDENTRY 2 0 2327099999999