ENTRY 23034 20130203 22342303400000001 SUBENT 23034001 20130203 22342303400100001 BIB 16 57 2303400100002 TITLE .Measurements and statistical model calculations of 2303400100003 activation cross-sections for 26Mg(n,a)23Ne reaction 2303400100004 between 13.6 and 14.9 MeV neutron energies 2303400100005 AUTHOR (A.Elmali, I.A.Reyhancan) 2303400100006 INSTITUTE (2TUKCNA) Cekmece Nuclear Research and Training Centre,2303400100007 Istanbul, Turkey. A.Elmal, I.A.Reyhancan, corespon- 2303400100008 ding author, Email: iskendera.reyhancan@taek.gov.tr 2303400100009 REFERENCE (J,ANE,35,1068,2008) Main reference, data are given 2303400100010 #doi:10.1016/j.anucene.2007.11.001 2303400100011 REL-REF (M,,B.Anders,R,GKSS-83/E/25,1983) Description of the 2303400100012 cyclic activation method 2303400100013 (I,22474001,M.Subasi+,J,NSE,122,423,1996)Exp.details. 2303400100014 (M,22787001,V.E.Lewis+,J,NIM,174,141,1980) Zr/Nb ratio 2303400100015 method details 2303400100016 (I,22478001,M.Subasi+,J,NSE,130,254,1998) Exp.details. 2303400100017 (I,22494001,M.Subasi+,J,NSE,135,260,2000) Exp.details. 2303400100018 FACILITY (VDG,2TUKCNA) Neutron generator SAMES T-400. D+ and 2303400100019 D++ ions with current 300 micro-A, accelerating 2303400100020 voltage 250 kV 2303400100021 INC-SOURCE (D-T) H-3(D,N)He-4 reaction using Ti-T target 2303400100022 INC-SPECT .Angles of irradiation position are 0, 30, 60, 90, 120,2303400100023 130 degree corresponding to neutron energies 14.86, 2303400100024 14.72, 14.46, 14.10, 13.68, 13.60 MeV. Effective inci-2303400100025 dent energies are determined by Zr/Nb ratio method 2303400100026 METHOD (ACTIV) Cyclic activation method 2303400100027 (SITA) Intermittent sample-monitor irradiation 2303400100028 DETECTOR (HPGE) For gamma ray detection from Mg-O sample 2303400100029 (SCIN) NE102A scintillation detector for neutron flux 2303400100030 determination with the help of Al2-O3 and Al 2303400100031 monitor samples 2303400100032 MONITOR (13-AL-27(N,P)12-MG-27,,SIG) 2303400100033 DECAY-MON (12-MG-27,9.458MIN,DG,843.8,0.73) 2303400100034 SAMPLE .Al2-O3 and metallic aluminium as monitor samples 2303400100035 CORRECTION .Corrections were made for the effects of gamma-ray 2303400100036 attenuation, random coincidence summing, dead time, 2303400100037 and scattered low energy neutron contribution 2303400100038 ERR-ANALYS (ERR-T) Total error includes errors due to: 2303400100039 (ERR-S) -Statistical error of gamma-ray photopeak 2303400100040 area error 2303400100041 (MONIT-ERR) -Effective neutron flux (reference Cross- 2303400100042 section) error 2303400100043 (ERR-1) -Sample weight error 2303400100044 (ERR-2) -Concentration of the element error 2303400100045 (ERR-3) -Relative gamma ray intensity error 2303400100046 (ERR-4) -Counting solid angle and intrinsic 2303400100047 efficiency of the gamma-ray detector error 2303400100048 (ERR-5) -Neutron flux fluctuation error 2303400100049 (ERR-6) -Irradiation, cooling and measuring times 2303400100050 error 2303400100051 (ERR-7) -Gamma-gamma coincidence summing error 2303400100052 (ERR-8) -Low energy neutrons error 2303400100053 (ERR-9) -Self-absorption of gamma rays error 2303400100054 HISTORY (20081106C) SM 2303400100055 (20101106A) SD: doi for ref. An.of Nucl.En.35 corrected2303400100056 Author's name corrected (A.Elmal => A.Elmali) 2303400100057 Three ref. moved to REL-REF. 2303400100058 (20130203U) SD: FACILITY was changed (LINAC -> VDG). 2303400100059 ENDBIB 57 0 2303400100060 COMMON 11 6 2303400100061 ERR-S MONIT-ERR ERR-1 ERR-2 ERR-3 ERR-4 2303400100062 ERR-5 ERR-6 ERR-7 ERR-8 ERR-9 2303400100063 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2303400100064 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2303400100065 2. 3. 0.1 0.1 0.2 3. 2303400100066 3. 0.1 1. 2. 0.1 2303400100067 ENDCOMMON 6 0 2303400100068 ENDSUBENT 67 0 2303400199999 SUBENT 23034002 20081106 22052303400200001 BIB 6 15 2303400200002 REACTION (12-MG-26(N,A)10-NE-23,,SIG) 2303400200003 DECAY-DATA (10-NE-23,37.24SEC,DG,439.99,0.329) 2303400200004 REL-REF (A,22281004,K.Kawade+,S,JAERI-M-92-020,199303) 2303400200005 (D,22434002,Y.Kasugai+,J,ANE,25,1485,1998) 2303400200006 (D,20898011,M.Bormann+,C,66PARIS,1,225,1966) 2303400200007 SAMPLE .Mg-O sample of the natural isotopic abundance in the 2303400200008 form of dense pellet 13 mm diameter, 8 mm thick, 2303400200009 weight 1.7 gram packed into thin polyethylene box. 2303400200010 Mg-26 content (11.01+- 0.03)% 2303400200011 ADD-RES (THEO) Theoretical calculations by STAPRE code 2303400200012 (exiton model) and optical model 2303400200013 ERR-ANALYS (ERR-HL) Error of half-life value given under 2303400200014 DECAY-DATA 2303400200015 (ERR-IDD) Error of intensity value given under 2303400200016 DECAY-DATA 2303400200017 ENDBIB 15 0 2303400200018 COMMON 2 3 2303400200019 ERR-HL ERR-IDD 2303400200020 SEC NO-DIM 2303400200021 0.12 0.001 2303400200022 ENDCOMMON 3 0 2303400200023 DATA 5 6 2303400200024 EN EN-ERR DATA ERR-T MONIT 2303400200025 MEV MEV MB MB MB 2303400200026 13.60 0.08 68.49 4.11 76.10 2303400200027 13.68 0.08 65.70 3.94 73.83 2303400200028 14.10 0.10 55.98 3.36 70.67 2303400200029 14.46 0.11 63.01 3.78 67.92 2303400200030 14.72 0.11 53.19 3.19 64.61 2303400200031 14.86 0.12 49.14 2.95 61.91 2303400200032 ENDDATA 8 0 2303400200033 ENDSUBENT 32 0 2303400299999 ENDENTRY 2 0 2303499999999