ENTRY 23238 20140603 22392323800000001 SUBENT 23238001 20140603 22392323800100001 BIB 17 133 2323800100002 TITLE Characterization of neutrons from a thick target 2323800100003 9Be(p,n) reaction by multiple foil activation technique2323800100004 for practical applications: 2323800100005 measurement of integral cross sections and their 2323800100006 comparison with integrated data from data files. 2323800100007 AUTHOR (M.S.Uddin,K.Kume,T.Takata,T.Hasegawa) 2323800100008 INSTITUTE (3BANSAV) M.S.Uddin. 2323800100009 (2JPNWER) K.Kume,T.Takata. 2323800100010 (2JPNJPN) Hasetech, 2-10-34-2 Matsushima, Tsuruga, 2323800100011 Fukui 914-0801, Japan. T.Hasegawa. 2323800100012 REFERENCE (J,RCA,102,369,2014) 2323800100013 #doi:10.1515/ract-2013-2168 2323800100014 REL-REF (M,31696001,M.S.Uddin+,J,ARI,68,1656,2010) 2323800100015 (M,23238001,M.S.Uddin+,J,RCA,101,613,2013) 2323800100016 Two references for method of neutron spectrum 2323800100017 unfolding. 2323800100018 (R,,A.A.Lychagin+,S,ISINN-10,333,2003) 2323800100019 Reference spectrum in calculation using the SULSA code.2323800100020 FACILITY (VDGT,2JPNWER) Tandem Accelerator, the Wakasa Wan 2323800100021 Energy Research Center (WERC), Japan. 2323800100022 INC-SOURCE (P-BE) 9Be(p,n) reaction. 7.685MeV proton beam. 2323800100023 8 mm diameter target. A beryllium piece of 1mm 2323800100024 thickness and 35mm diameter was mounted in a hole of 2323800100025 stainless steel container. The beryllium was backed on 2323800100026 downstream by a stainless steel pellet of 2 mm 2323800100027 thickness. A 10 mm thick and 35 mm inside diameter 2323800100028 polyethylene ring was fastened between two 12mm thick 2323800100029 stainless steel of the same inside diameter. 2323800100030 INC-SPECT Measured and calculated specific activities of the 2323800100031 reaction products were used for neutron spectrum 2323800100032 unfolding: 2323800100033 Reaction Measured Calcul. Error of Error of2323800100034 specific specific measur-t calc-n 2323800100035 activity activity (%) (%) 2323800100036 (dps/nucl.) (dps/nucl.) 2323800100037 27Al(n,p)27Mg 2.57E-20 2.40E-20 5.4 6.2 2323800100038 46Ti(n,p)46Sc 7.60E-20 8.80E-20 10.0 3.8 2323800100039 47Ti(n,p)47Sc 1.89E-19 1.82E-19 5.0 3.5 2323800100040 54Fe(n,p)54Mn 8.64E-19 8.21E-19 5.9 4.0 2323800100041 58Ni(n,p)58Co 1.00E-18 9.63E-19 5.1 3.9 2323800100042 92Mo(n,p)92mNb 6.17E-20 6.61E-20 5.1 4.9 2323800100043 113In(n,inl)113mIn 1.82E-18 1.85E-18 5.5 4.0 2323800100044 115In(n,inl)115mIn 2.13E-18 2.09E-18 5.4 3.9 2323800100045 197Au(n,g)198Au 3.03E-18 3.06E-18 5.4 7.0 2323800100046 For calculation the excitation functions for those 2323800100047 reactions, covering the energies from 0.1 to 5.85 MeV 2323800100048 were taken from the IRDF-2004, TENDL-2011 etc. 2323800100049 The 115In(n,inl)115mIn reaction was used as monitor to 2323800100050 measure the total fast neutron flux for energies above 2323800100051 0.37MeV. The 58Ni(n,p)58Co reaction was also used to 2323800100052 measure the fast neutron flux for a check of value 2323800100053 obtained from the other monitor reaction.The cross 2323800100054 section value averaged for the unfolded spectrum 2323800100055 was calculated - 90mb for the 58Ni(n,p) reaction and 2323800100056 182mb for the 115In(n,inl) reaction and then those 2323800100057 values were used for fast flux determination. 2323800100058 The thermal neutron flux at various positions in the 2323800100059 downstream was determined using the 197Au(n,g)198Au 2323800100060 reaction as monitor. 2323800100061 The unfolded neutron spectrum over the energy range of 2323800100062 0.1 to 5.85 MeV at 10 cm distance from the target in 2323800100063 the 0.deg direction with respect to the incident proton2323800100064 beam of 7.685MeV is shown in Fig.3 of RCA,102,369,2014.2323800100065 Uncertainty of about 6% to the various regions of the 2323800100066 spectrum. In unfolding of spectrum the value of KHI**2 2323800100067 was 1.835. 2323800100068 The spectrum reported by A.A.Lychagin+ was used as 2323800100069 reference spectrum in calculation using the SULSA code.2323800100070 Neutron flux at 10 cm in the 0deg direction: 2323800100071 Energy region Flux (n cm-2 s-1) 2323800100072 Thermal 3.08E+4 2323800100073 Epithermal 8.39E+3 2323800100074 0.1-0.3MeV 1.60E+5 2323800100075 0.3-5.85MeV 1.24E+7 2323800100076 METHOD (ACTIV,STTA,CADMB,GSPEC) To measure the fluxes of the 2323800100077 thermal and epithermal neutrons, Au foils and Au foils 2323800100078 covered with Cd were fastened in the ring at 0.,20.,40,2323800100079 60. degrees positions. The irradiation was performed 2323800100080 for 4h and 30min, during which the proton beam current 2323800100081 was kept constant at 0.91 microA and its incident 2323800100082 energy was 7.685 MeV. 2323800100083 SAMPLE High purity foils of metals Al, Ti, Fe, Ni, Mo, In, Au 2323800100084 were cut in circular discs with 1.5cm diameter and 2323800100085 placed in an Al-container. All foils in a stack were 2323800100086 irradiated together with neutrons at 0. deg position 2323800100087 with respect to the direction of the proton beam which 2323800100088 is about 10 cm downstream. To measure the fluxes of 2323800100089 the thermal and epithermal neutrons, 99.99% purity Au 2323800100090 foils and Au foils covered with Cd were fastened in 2323800100091 the ring at 0., 20., 40. and 60. positions. 2323800100092 Ni sample of purity (Supplier NILACO) 99.0%, 2323800100093 In sample of purity 99.99% (Supplier NILACO), 2323800100094 Au sample of 99.9% purity (Supplier Tanaka Kikinzoku 2323800100095 Koguo) were used for monitoring. 2323800100096 DETECTOR (HPGE) The radioactivity produced in each foil was 2323800100097 measured non-destructively using a high purity 2323800100098 germanium (HPGe) gamma-ray detector GEM20-P,ORTEC. 2323800100099 All samples were counted directly on the surface of 2323800100100 the detector. In foil was also counted at 10 cm 2323800100101 from the detector surface. The obtained 115m-In 2323800100102 activity at 10 cm was considered as standard value to 2323800100103 determine the detector efficiency for the extended 2323800100104 sample on the surface.The gamma-ray spectrum was 2323800100105 analyzed by GammaVision software. The efficiency vs. 2323800100106 energy curve of the HPGe detector was determined using 2323800100107 the standard point sources 57Co, 60Co, 133Ba and 152Eu.2323800100108 The efficiency for an extended sample (dia. 1.5 cm) on 2323800100109 the surface of the detector was found to be 7.5% lower 2323800100110 than that for a point source. 2323800100111 MONITOR ((MONIT1)28-NI-58(N,P)27-CO-58,,SIG,,SPA) 2323800100112 ((MONIT2)49-IN-115(N,INL)49-IN-115-M,,SIG,,SPA) 2323800100113 DECAY-MON (27-CO-58-G,70.86D,DG,811.0,0.990) 2323800100114 Q-value 0.40 MeV, threshold energy 0.0 MeV, 2323800100115 reaction threshold 0.5 MeV. 2323800100116 (49-IN-115-M,4.49HR,DG,336.2,0.4583) 2323800100117 Q-value -0.34 MeV, threshold energy 0.34 MeV, 2323800100118 reaction threshold 0.34 MeV. 2323800100119 CORRECTION The uncertainty due to random coincidences was 2323800100120 negligible. 2323800100121 The effect of real coincidences was also considered. 2323800100122 The most of the investigated radionuclides have 2323800100123 simple decay schemes - no coincidence loss is expected.2323800100124 Only for 27Mg and 46Sc, appreciable loss is possible. 2323800100125 True coincidence losses for 27Mg and 46Sc estimated 2323800100126 were about 14% and 24%, respectively. 2323800100127 Usual corrections, like the intensity of the gamma-ray 2323800100128 used, the efficiency of the detector,etc. 2323800100129 ERR-ANALYS (DATA-ERR) Total uncertainties in the measured integral2323800100130 cross sections 7.-11 % . 2323800100131 STATUS (TABLE) Data from Table 4 of RCA,102,(5),369,2014. 2323800100132 Decay data from Table 1 of RCA,102,(5),369,2014 were 2323800100133 taken by authors from NUDAT,2009. 2323800100134 HISTORY (20140603C) M.M. 2323800100135 ENDBIB 133 0 2323800100136 COMMON 3 3 2323800100137 EN-MIN MONIT1 MONIT2 2323800100138 MEV MB MB 2323800100139 0.3 90. 182. 2323800100140 ENDCOMMON 3 0 2323800100141 ENDSUBENT 140 0 2323800199999 SUBENT 23238002 20140603 22392323800200001 BIB 4 14 2323800200002 REACTION (13-AL-27(N,P)12-MG-27,,SIG,,SPA) 2323800200003 SAMPLE Purity (Supplier NILACO) 99.0% . 2323800200004 DECAY-DATA (12-MG-27,9.46MIN,DG,843.7,0.718) 2323800200005 Q-value -1.83 MeV, threshold energy 1.90 MeV, 2323800200006 reaction threshold 3.0 MeV. 2323800200007 ADD-RES (COMP) Measured c-s were compared with calculated by 2323800200008 evaluated data libraries: 2323800200009 Eval.libraries Calc.spect.av.c-s,mb Calc./Measur. 2323800200010 ENDF/B-VII 1.88 0.90 2323800200011 IRDF-2002 1.84 0.88 2323800200012 TENDL-2011 2.0 0.95 2323800200013 JEFF-3.1 1.93 0.92 2323800200014 JENDL-4 2.0 0.95 2323800200015 ROSFOND-2010 1.93 0.92 2323800200016 ENDBIB 14 0 2323800200017 NOCOMMON 0 0 2323800200018 DATA 2 1 2323800200019 DATA DATA-ERR 2323800200020 MB MB 2323800200021 2.1 0.13 2323800200022 ENDDATA 3 0 2323800200023 ENDSUBENT 22 0 2323800299999 SUBENT 23238003 20140603 22392323800300001 BIB 4 14 2323800300002 REACTION (22-TI-46(N,P)21-SC-46,,SIG,,SPA) 2323800300003 SAMPLE Purity (Supplier NILACO) 99.5% . 2323800300004 DECAY-DATA (21-SC-46-G,83.82D,DG,889.0,0.9998) 2323800300005 Q-value -1.58 MeV, threshold energy 1.62 MeV, 2323800300006 reaction threshold 2.0 MeV. 2323800300007 ADD-RES (COMP) Measured c-s were compared with calculated by 2323800300008 evaluated data libraries: 2323800300009 Eval.libraries Calc.spect.av.c-s,mb Calc./Measur. 2323800300010 ENDF/B-VII 6.5 1.08 2323800300011 IRDF-2002 5.3 0.9 2323800300012 TENDL-2011 5.2 0.9 2323800300013 JEFF-3.1 5.1 0.85 2323800300014 JENDL-4 6.9 1.15 2323800300015 ROSFOND-2010 6.9 1.15 2323800300016 ENDBIB 14 0 2323800300017 NOCOMMON 0 0 2323800300018 DATA 2 1 2323800300019 DATA DATA-ERR 2323800300020 MB MB 2323800300021 6.0 0.7 2323800300022 ENDDATA 3 0 2323800300023 ENDSUBENT 22 0 2323800399999 SUBENT 23238004 20140603 22392323800400001 BIB 4 14 2323800400002 REACTION (22-TI-47(N,P)21-SC-47,,SIG,,SPA) 2323800400003 SAMPLE Purity (Supplier NILACO) 99.5% . 2323800400004 DECAY-DATA (21-SC-47,3.35D,DG,159.3,0.683) 2323800400005 Q-value 0.18 MeV, threshold energy 0.0 MeV, 2323800400006 reaction threshold 1.5 MeV. 2323800400007 ADD-RES (COMP) Measured c-s were compared with calculated by 2323800400008 evaluated data libraries: 2323800400009 Eval.libraries Calc.spect.av.c-s,mb Calc./Measur. 2323800400010 ENDF/B-VII 15.8 1.01 2323800400011 IRDF-2002 15.7 1.0 2323800400012 TENDL-2011 15.8 1.01 2323800400013 JEFF-3.1 17.1 1.09 2323800400014 JENDL-4 15.4 0.98 2323800400015 ROSFOND-2010 15.4 0.98 2323800400016 ENDBIB 14 0 2323800400017 NOCOMMON 0 0 2323800400018 DATA 2 1 2323800400019 DATA DATA-ERR 2323800400020 MB MB 2323800400021 15.7 1.3 2323800400022 ENDDATA 3 0 2323800400023 ENDSUBENT 22 0 2323800499999 SUBENT 23238005 20140603 22392323800500001 BIB 4 14 2323800500002 REACTION (26-FE-54(N,P)25-MN-54,,SIG,,SPA) 2323800500003 SAMPLE Purity (Supplier NILACO) 99.5% . 2323800500004 DECAY-DATA (25-MN-54,312.20D,DG,834.9,0.9998) 2323800500005 Q-value 0.08 MeV, threshold energy 0.0 MeV, 2323800500006 reaction threshold 1.7 MeV. 2323800500007 ADD-RES (COMP) Measured c-s were compared with calculated by 2323800500008 evaluated data libraries: 2323800500009 Eval.libraries Calc.spect.av.c-s,mb Calc./Measur. 2323800500010 ENDF/B-VII 69.94 1.0 2323800500011 IRDF-2002 69.8 1.0 2323800500012 TENDL-2011 70.8 1.01 2323800500013 JEFF-3.1 68.4 0.98 2323800500014 JENDL-4 70.0 1.0 2323800500015 ROSFOND-2010 68.4 0.98 2323800500016 ENDBIB 14 0 2323800500017 NOCOMMON 0 0 2323800500018 DATA 2 1 2323800500019 DATA DATA-ERR 2323800500020 MB MB 2323800500021 69.9 5.6 2323800500022 ENDDATA 3 0 2323800500023 ENDSUBENT 22 0 2323800599999 SUBENT 23238006 20140603 22392323800600001 BIB 4 7 2323800600002 REACTION (42-MO-92(N,P)41-NB-92-M,,SIG,,SPA) 2323800600003 SAMPLE Purity (Supplier NILACO) 99.95% . 2323800600004 DECAY-DATA (41-NB-92-M,10.15D,DG,934.5,0.990) 2323800600005 Q-value 0.29 MeV, threshold energy 0.0 MeV, 2323800600006 reaction threshold 2.25 MeV. 2323800600007 REL-REF (A,,S.M.Qaim+,J,PR/C,40,1993,1989) 6.1 mb. 2323800600008 (A,,,R,IAEA-TECDOC-1285,2002) 6.4 mb. 2323800600009 ENDBIB 7 0 2323800600010 NOCOMMON 0 0 2323800600011 DATA 2 1 2323800600012 DATA DATA-ERR 2323800600013 MB MB 2323800600014 6.3 0.6 2323800600015 ENDDATA 3 0 2323800600016 ENDSUBENT 15 0 2323800699999 SUBENT 23238007 20140603 22392323800700001 BIB 4 8 2323800700002 REACTION (49-IN-113(N,INL)49-IN-113-M,,SIG,,SPA) 2323800700003 SAMPLE Purity (Supplier NILACO) 99.99% . 2323800700004 DECAY-DATA (49-IN-113-M,1.66HR,DG,391.7,0.642) 2323800700005 Q-value -0.39 MeV, threshold energy 0.39 MeV, 2323800700006 reaction threshold 0.39 MeV. 2323800700007 ADD-RES (COMP) Measured c-s were compared with calculated by 2323800700008 evaluated data libraries ENDF/B-VII, IRDF-2002, 2323800700009 TENDL-2011, JEFF-3.1, JENDL-4, ROSFOND-2010 - 148.1 mb.2323800700010 ENDBIB 8 0 2323800700011 NOCOMMON 0 0 2323800700012 DATA 2 1 2323800700013 DATA DATA-ERR 2323800700014 MB MB 2323800700015 159.0 12.7 2323800700016 ENDDATA 3 0 2323800700017 ENDSUBENT 16 0 2323800799999 ENDENTRY 7 0 2323899999999