ENTRY 22744 20120821 22332274400000001 SUBENT 22744001 20120821 22332274400100001 BIB 11 41 2274400100002 REFERENCE (C,2004SANTA,1,996,2004) 2274400100003 (J,ANE,43,106,2012) First author M.Shibata. 2274400100004 #doi:10.1016/j.anucene.2012.01.005 2274400100005 TITLE Reliability of prompt gamma-ray intensities for the 2274400100006 measurement of neutron capture cross sections. 2274400100007 AUTHOR (I.Miyazaki, T.Shimizu,M.Shibata, K.Kawade,A.Taniguchi,2274400100008 H.Harada, K.Furutaka, H.Sakane, H.Hayashi,A.Tojo, 2274400100009 M.Furata, Y.Kojima) 2274400100010 INSTITUTE (2JPNKTO) Taniguchi - Research Reactor Institute 2274400100011 (2JPNNAG) Miyazaki, Shimizu 2274400100012 -Department of Energy Engineering and Science. 2274400100013 Kawade 2274400100014 -Department of Materials,Physics and Energy Engineering2274400100015 Shibata 2274400100016 -Radioisotope Research Center. 2274400100017 (2JPNJNC) Harada, Furutaka, Sakane 2274400100018 FACILITY (REAC,2JPNKTO) Reactor KUR of Kyoto University 2274400100019 INC-SOURCE (REAC) Supermirror neutron guide tube at Kyoto 2274400100020 University Research Reactor Institute. 2274400100021 INC-SPECT .Not given explicitly. Supposed Maxwellian by 2274400100022 compiler. Neutron flux 5.E+7 n/cm**2/sec. 2274400100023 METHOD (GSPEC) Prompt-gamma rays method. 2274400100024 (ACTIV) Measurement by using gamma-rays following 2274400100025 beta-decay. 2274400100026 DETECTOR (HPGE) Four detectors of 22% and 38% HPGe, 90% HPGe and2274400100027 90% GAMMA-X HPGe. Distance from each detector to 2274400100028 sample 5.0cm in C,2007NICE, 10 cm in J,ANE,43,106. 2274400100029 Lithium fluoride Li-6F shielding. 2274400100030 Efficiency was determined from thermal neutron capture2274400100031 gamma-rays of N-14(n,g) reaction.Data of absolute 2274400100032 intensities of decay and prompt gamma-rays were taken 2274400100033 from REL-REFs. 2274400100034 REL-REF (I,,T.Akiyoshi+,J,NST,29,939,1992) 2274400100035 HISTORY (20070722C) M.M./S.M. 2274400100036 (20070729A) Last corrections have been done - SM 2274400100037 (20120821A) M.M. Reference J,ANE,43,106,2012 was added.2274400100038 Subents 011-018 were added. 2274400100039 BIB information was updated. 2274400100040 Subents 002-010 ( ratios of measure c-s GSPEC to 2274400100041 ACTIV methods) were deleted according to the comment 2274400100042 of N.Otsuka (NDS, IAEA). 2274400100043 ENDBIB 41 0 2274400100044 COMMON 3 3 2274400100045 EN-DUMMY ERR-1 ERR-2 2274400100046 EV PER-CENT PER-CENT 2274400100047 0.0253 5. 1. 2274400100048 ENDCOMMON 3 0 2274400100049 ENDSUBENT 48 0 2274400199999 NOSUBENT 22744002 20120821 22332274400200001 NOSUBENT 22744003 20120821 22332274400300001 NOSUBENT 22744004 20120821 22332274400400001 NOSUBENT 22744005 20120821 22332274400500001 NOSUBENT 22744006 20120821 22332274400600001 NOSUBENT 22744007 20120821 22332274400700001 NOSUBENT 22744008 20120821 22332274400800001 NOSUBENT 22744009 20120821 22332274400900001 NOSUBENT 22744010 20120821 22332274401000001 SUBENT 22744011 20120821 22332274401100001 BIB 11 70 2274401100002 REACTION (11-NA-23(N,G)11-NA-24,,SPC,,MXW) 2274401100003 Emission probabilities for some intense prompt gamma 2274401100004 rays. 2274401100005 DECAY-DATA (11-NA-24,14.95HR,DG,1366.625,0.999936) 2274401100006 1368.626+-0.00 keV, 99.9936+-0.0015 % . 2274401100007 REL-REF (R,,R.B.Firestone+,B,FIRESTONE,,1996) 2274401100008 HL, Egamma, intensity were taken from Firestone and 2274401100009 Shirley (1996). 2274401100010 (A,,P.Hungerford+,J,ZP/A,313,325,1983) 2274401100011 Z.Revay,R.B.Firestone,T.Belgya,G.L.Molnar, 2004. Prompt2274401100012 gamma-ray spectrum catalog. In: Molnar, G.L.(Ed.), 2274401100013 Handbook of Prompt Gamma Activation Analysis With 2274401100014 Neutron Beams. Kuwer Academic Publishers, pp.173-364. 2274401100015 The values by Z.Revay+,2004 and by P.Hungerford+,1983 2274401100016 were almost in agreement with the present ones. 2274401100017 (A,21862001,T.A.A.Tielens+,J,NP/A,403,13,1983) 2274401100018 The values by Tielens+,1983 were smaller than the 2274401100019 present ones in low energy region below 1 MeV, 2274401100020 nevertheless, they were also almost in agreement with 2274401100021 the present ones. 2274401100022 INC-SPECT Thermal neutron flux 2.E+7 n/cm**2/sec under 5 MW 2274401100023 operation. 2274401100024 The neutron beam at the irradiation position was 2274401100025 approximately 14x61 mm2. 2274401100026 The fluctuation of neutron flux was monitored by 198Au 2274401100027 activity by inserting the 197Au sample approximately 2274401100028 every 6 h. The fluctuation was determined to be small 2274401100029 enough not to have affected the measurements. 2274401100030 SAMPLE (11-NA-23,NAT=1.00) Natural sample. 2274401100031 Powder sample was wrapped in waxed paper. 2274401100032 The samples were located on a holder made of graphite, 2274401100033 and they were set at a 30 deg angle to the detector in 2274401100034 the target box. 2274401100035 Na-23 abundance 100.%, chemical form NaF powder, 2274401100036 thickness 1.1 mm, weight 176.1 mg. 2274401100037 tmp(=ti) 8.3 hr, tmd 2.6 hr; 2274401100038 tmp - time of prompt gamma measuring, 2274401100039 ti - irradiation time, 2274401100040 tmd - time of beta-delayed gamma-ray measuring. 2274401100041 METHOD (GSPEC) The prompt and beta-delayed gamma-rays were 2274401100042 measured with well calibrated 22% HPGe detector during 2274401100043 irradiation and after irradiation, respectively. 2274401100044 Relative detection efficiencies of the HPGe detector 2274401100045 were determined using radioactive sources 56Co, 133Ba, 2274401100046 152Eu, (Firestone and Shirley, 1996; IAEA, 1991), 2274401100047 and the prompt gamma rays from the 14N(n,c)15N 2274401100048 (Miyazaki et al.,2008), and Monte Carlo simulation 2274401100049 code (GEANT4) (Agostinelli et al., 2003). 2274401100050 The uncertainties in the efficiency curve were 2274401100051 evaluated to be within 0.7% at energies between 0.122 2274401100052 and 5 MeV, and 1.0% above 5 MeV. 2274401100053 EN-SEC (E,G) Energy of prompt gamma rays were taken from 2274401100054 Z.Revay,R.B.Firestone,T.Belgya,G.L.Molnar, 2004. Prompt2274401100055 gamma-ray spectrum catalog. In: Molnar, G.L.(Ed.), 2274401100056 Handbook of Prompt Gamma Activation Analysis With 2274401100057 Neutron Beams. Kuwer Academic Publishers, pp.173-364. 2274401100058 CORRECTION For pile-up loses caused by accidental coincidence- 2274401100059 0.38-3.6 %. 2274401100060 The correction for coincidence summing effects was 2274401100061 approximately 5% of the all corrections. 2274401100062 For self-absorption of target material, absorption by 2274401100063 material of target box, and escape ratios. 2274401100064 ERR-ANALYS (ERR-T) Uncertainties were evaluated from the 2274401100065 experimental uncertainties inherent in the counting 2274401100066 statistics, the detection efficiency including total 2274401100067 efficiency for correction of summing effect, the escape2274401100068 ratio, peak evaluation and adopted nuclear data 2274401100069 themselves. 2274401100070 STATUS (TABLE) Table 2 of J,ANE,43,106,2012. 2274401100071 HISTORY (20120821C) M.M 2274401100072 ENDBIB 70 0 2274401100073 NOCOMMON 0 0 2274401100074 DATA 3 12 2274401100075 E DATA ERR-T 2274401100076 KEV PC/REAC PC/REAC 2274401100077 472.20 92.0 1.4 2274401100078 563.19 1.69 0.05 2274401100079 869.21 20.7 0.3 2274401100080 874.39 14.3 0.2 2274401100081 1344.6 3.97 0.08 2274401100082 2025.2 7.1 0.1 2274401100083 2030.3 4.5 0.1 2274401100084 2414.5 4.5 0.1 2274401100085 2517.8 13.2 0.3 2274401100086 3587.5 11.4 0.2 2274401100087 3981.5 12.7 0.2 2274401100088 6395.5 18.5 0.3 2274401100089 ENDDATA 14 0 2274401100090 ENDSUBENT 89 0 2274401199999 SUBENT 22744012 20120821 22332274401200001 BIB 11 69 2274401200002 REACTION (13-AL-27(N,G)13-AL-28,,SPC,,MXW) 2274401200003 Emission probabilities for some intense prompt gamma 2274401200004 rays. 2274401200005 DECAY-DATA (13-AL-28,2.241MIN,DG,1778.969,1.00) 2274401200006 1778.969+-0.012 keV. 2274401200007 REL-REF (R,,R.B.Firestone+,B,FIRESTONE,,1996) 2274401200008 HL, Egamma, intensity were taken from Firestone and 2274401200009 Shirley (1996). 2274401200010 (A,,H.H.Schmidt+,J,PR/C,25,2888,1982) 2274401200011 Z.Revay,R.B.Firestone,T.Belgya,G.L.Molnar, 2004. Prompt2274401200012 gamma-ray spectrum catalog. In: Molnar, G.L.(Ed.), 2274401200013 Handbook of Prompt Gamma Activation Analysis With 2274401200014 Neutron Beams. Kuwer Academic Publishers, pp.173-364. 2274401200015 The values by Z.Revay+,2004 except for the 7724-keV c 2274401200016 gamma-ray and the values by H.Schmidt+,1982 are in 2274401200017 agreement with the present ones within 10% 2274401200018 uncertainties. 2274401200019 INC-SPECT Thermal neutron flux 2.E+7 n/cm**2/sec under 5 MW 2274401200020 operation. 2274401200021 The neutron beam at the irradiation position was 2274401200022 approximately 14x61 mm2. 2274401200023 The fluctuation of neutron flux was monitored by 198Au 2274401200024 activity by inserting the 197Au sample approximately 2274401200025 every 6 h. The fluctuation was determined to be small 2274401200026 enough not to have affected the measurements. 2274401200027 SAMPLE (13-AL-27,NAT=1.00) Natural samples for 27Al . 2274401200028 Metal foil sample of 10x10 mm2. 2274401200029 The samples were located on a holder made of graphite, 2274401200030 and they were set at a 30 deg angle to the detector in 2274401200031 the target box. 2274401200032 27Al abundance 100.%, chemical form - Al metal, 2274401200033 thickness 0.2 mm, weight 102.8 mg, 2274401200034 tmp(=ti) 30.6 hr, tmd 0.7 hr, 2274401200035 The cycle of ti about 6 h and tmd about 5 min was 2274401200036 iterated five times; 2274401200037 tmp - time of prompt gamma measuring, 2274401200038 ti - irradiation time, 2274401200039 tmd - time of beta-delayed gamma-ray measuring. 2274401200040 METHOD (GSPEC) The prompt and beta-delayed gamma-rays were 2274401200041 measured with well calibrated 22% HPGe detector during 2274401200042 irradiation and after irradiation, respectively. 2274401200043 Relative detection efficiencies of the HPGe detector 2274401200044 were determined using radioactive sources 56Co, 133Ba, 2274401200045 152Eu, (Firestone and Shirley, 1996; IAEA, 1991), 2274401200046 and the prompt gamma rays from the 14N(n,c)15N 2274401200047 (Miyazaki et al.,2008), and Monte Carlo simulation 2274401200048 code (GEANT4) (Agostinelli et al., 2003). 2274401200049 The uncertainties in the efficiency curve were 2274401200050 evaluated to be within 0.7% at energies between 0.122 2274401200051 and 5 MeV, and 1.0% above 5 MeV. 2274401200052 EN-SEC (E,G) Energy of prompt gamma rays were taken from 2274401200053 Z.Revay,R.B.Firestone,T.Belgya,G.L.Molnar, 2004. Prompt2274401200054 gamma-ray spectrum catalog. In: Molnar, G.L.(Ed.), 2274401200055 Handbook of Prompt Gamma Activation Analysis With 2274401200056 Neutron Beams. Kuwer Academic Publishers, pp.173-364. 2274401200057 CORRECTION For pile-up loses caused by accidental coincidence- 2274401200058 0.38-3.6 %. 2274401200059 The correction for coincidence summing effects was 2274401200060 approximately 5% of the all corrections. 2274401200061 For self-absorption of target material, absorption by 2274401200062 material of target box, and escape ratios. 2274401200063 ERR-ANALYS (ERR-T) Uncertainties were evaluated from the 2274401200064 experimental uncertainties inherent in the counting 2274401200065 statistics, the detection efficiency including total 2274401200066 efficiency for correction of summing effect, the escape2274401200067 ratio, peak evaluation and adopted nuclear data 2274401200068 themselves. 2274401200069 STATUS (TABLE) Table 2 of J,ANE,43,106,2012. 2274401200070 HISTORY (20120821C) M.M 2274401200071 ENDBIB 69 0 2274401200072 NOCOMMON 0 0 2274401200073 DATA 3 8 2274401200074 E DATA ERR-T 2274401200075 KEV PC/REAC PC/REAC 2274401200076 1622.9 4.19 0.10 2274401200077 3033.9 7.64 0.22 2274401200078 3465.1 6.44 0.16 2274401200079 3591.2 4.76 0.13 2274401200080 4133.4 6.47 0.16 2274401200081 4690.7 5.15 0.16 2274401200082 7693.4 3.24 0.10 2274401200083 7724.0 27.86 0.55 2274401200084 ENDDATA 10 0 2274401200085 ENDSUBENT 84 0 2274401299999 SUBENT 22744013 20120821 22332274401300001 BIB 11 67 2274401300002 REACTION (23-V-51(N,G)23-V-52,,SPC,,MXW) 2274401300003 Emission probabilities for some intense prompt gamma 2274401300004 rays. 2274401300005 DECAY-DATA (23-V-52,3.743MIN,DG,1434.068,1.00) 2274401300006 1434.068+-0.014 keV, 100.+-1. % 2274401300007 REL-REF (R,,R.B.Firestone+,B,FIRESTONE,,1996) 2274401300008 HL, Egamma, intensity were taken from Firestone and 2274401300009 Shirley (1996). 2274401300010 (D,,S.Michaelsen+,J,ZP/A,338,371,1991) 2274401300011 Z.Revay,R.B.Firestone,T.Belgya,G.L.Molnar, 2004. Prompt2274401300012 gamma-ray spectrum catalog. In: Molnar, G.L.(Ed.), 2274401300013 Handbook of Prompt Gamma Activation Analysis With 2274401300014 Neutron Beams. Kuwer Academic Publishers, pp.173-364. 2274401300015 The values by Z.Revay+,2004 and S.Michaelsen+,1991 are 2274401300016 systematically 10% smaller than the present ones. 2274401300017 INC-SPECT Thermal neutron flux 2.E+7 n/cm**2/sec under 5 MW 2274401300018 operation. 2274401300019 The neutron beam at the irradiation position was 2274401300020 approximately 14x61 mm2. 2274401300021 The fluctuation of neutron flux was monitored by 198Au 2274401300022 activity by inserting the 197Au sample approximately 2274401300023 every 6 h. The fluctuation was determined to be small 2274401300024 enough not to have affected the measurements. 2274401300025 SAMPLE (23-V-51,NAT=0.99750) Natural sample for 51V, 2274401300026 Powder samples were wrapped in waxed paper. 2274401300027 The samples were located on a holder made of graphite, 2274401300028 and they were set at a 30 deg angle to the detector in 2274401300029 the target box. 2274401300030 51V abundance 99.750 %, chemical form V2O5 powder, 2274401300031 Thickness 1.5 mm, weight 90.0 mg, 2274401300032 tmp(=ti) 17.5 hr, tmd 0.8 hr, 2274401300033 the cycle of ti about 6 h and tmd about 17 min was 2274401300034 iterated three times, 2274401300035 tmp - time of prompt gamma measuring, 2274401300036 ti - irradiation time, 2274401300037 tmd - time of beta-delayed gamma-ray measuring. 2274401300038 METHOD (GSPEC) The prompt and beta-delayed gamma-rays were 2274401300039 measured with well calibrated 22% HPGe detector during 2274401300040 irradiation and after irradiation, respectively. 2274401300041 Relative detection efficiencies of the HPGe detector 2274401300042 were determined using radioactive sources 56Co, 133Ba, 2274401300043 152Eu, (Firestone and Shirley, 1996; IAEA, 1991), 2274401300044 and the prompt gamma rays from the 14N(n,c)15N 2274401300045 (Miyazaki et al.,2008), and Monte Carlo simulation 2274401300046 code (GEANT4) (Agostinelli et al., 2003). 2274401300047 The uncertainties in the efficiency curve were 2274401300048 evaluated to be within 0.7% at energies between 0.122 2274401300049 and 5 MeV, and 1.0% above 5 MeV. 2274401300050 EN-SEC (E,G) Energy of prompt gamma rays were taken from 2274401300051 Z.Revay,R.B.Firestone,T.Belgya,G.L.Molnar, 2004. Prompt2274401300052 gamma-ray spectrum catalog. In: Molnar, G.L.(Ed.), 2274401300053 Handbook of Prompt Gamma Activation Analysis With 2274401300054 Neutron Beams. Kuwer Academic Publishers, pp.173-364. 2274401300055 CORRECTION For pile-up loses caused by accidental coincidence- 2274401300056 0.38-3.6 %. 2274401300057 The correction for coincidence summing effects was 2274401300058 approximately 5% of the all corrections. 2274401300059 For self-absorption of target material, absorption by 2274401300060 material of target box, and escape ratios. 2274401300061 ERR-ANALYS (ERR-T) Uncertainties were evaluated from the 2274401300062 experimental uncertainties inherent in the counting 2274401300063 statistics, the detection efficiency including total 2274401300064 efficiency for correction of summing effect, the escape2274401300065 ratio, peak evaluation and adopted nuclear data 2274401300066 themselves. 2274401300067 STATUS (TABLE) Table 2 of J,ANE,43,106,2012. 2274401300068 HISTORY (20120821C) M.M 2274401300069 ENDBIB 67 0 2274401300070 NOCOMMON 0 0 2274401300071 DATA 3 10 2274401300072 E DATA ERR-T 2274401300073 KEV PC/REAC PC/REAC 2274401300074 436.63 8.94 0.12 2274401300075 845.95 5.59 0.08 2274401300076 1558.8 7.07 0.10 2274401300077 5515.8 9.26 0.15 2274401300078 5752.1 9.04 0.15 2274401300079 6464.9 9.66 0.16 2274401300080 6517.3 16.97 0.25 2274401300081 6874.2 10.63 0.17 2274401300082 7162.9 13.28 0.20 2274401300083 7310.7 5.58 0.10 2274401300084 ENDDATA 12 0 2274401300085 ENDSUBENT 84 0 2274401399999 SUBENT 22744014 20120821 22332274401400001 BIB 11 67 2274401400002 REACTION (25-MN-55(N,G)25-MN-56,,SPC,,MXW) 2274401400003 Emission probabilities for some intense prompt gamma 2274401400004 rays. 2274401400005 DECAY-DATA (25-MN-56,2.578HR,DG,846.754,0.9887) 2274401400006 846.754+-0.020 keV, 98.87+-0.30 % . 2274401400007 REL-REF (R,,R.B.Firestone+,B,FIRESTONE,,1996) 2274401400008 HL, Egamma, intensity were taken from Firestone and 2274401400009 Shirley (1996). 2274401400010 (D,,A.H.Colenbrander+,J,CJP,53,236,1975) 2274401400011 (D,,T.J.Kennett+,J,CJP,59,1212,1981) 2274401400012 Z.Revay,R.B.Firestone,T.Belgya,G.L.Molnar, 2004. Prompt2274401400013 gamma-ray spectrum catalog. In: Molnar, G.L.(Ed.), 2274401400014 Handbook of Prompt Gamma Activation Analysis With 2274401400015 Neutron Beams. Kuwer Academic Publishers, pp.173-364. 2274401400016 The values by Z.Revay+,2004 are systematically smaller 2274401400017 than the present ones. The values by A.H.Colenbrander 2274401400018 and T.J.Kennett+,1975 are larger than the present ones.2274401400019 INC-SPECT Thermal neutron flux 2.E+7 n/cm**2/sec under 5 MW 2274401400020 operation. 2274401400021 The neutron beam at the irradiation position was 2274401400022 approximately 14x61 mm2. 2274401400023 The fluctuation of neutron flux was monitored by 198Au 2274401400024 activity by inserting the 197Au sample approximately 2274401400025 every 6 h. The fluctuation was determined to be small 2274401400026 enough not to have affected the measurements. 2274401400027 SAMPLE (25-MN-55,NAT=1.00) Natural sample for 55Mn. 2274401400028 Powder samples were wrapped in waxed paper. 2274401400029 The samples were located on a holder made of graphite, 2274401400030 and they were set at a 30 deg angle to the detector in 2274401400031 the target box. 2274401400032 55Mn abundance 100.%, chemical form Mn powder, 2274401400033 thickness 0.8 mm, weight 49.7 mg, 2274401400034 tmp(=ti) 12.0 hr, tmd 0.5 hr, 2274401400035 tmp - time of prompt gamma measuring, 2274401400036 ti - irradiation time, 2274401400037 tmd - time of beta-delayed gamma-ray measuring. 2274401400038 METHOD (GSPEC) The prompt and beta-delayed gamma-rays were 2274401400039 measured with well calibrated 22% HPGe detector during 2274401400040 irradiation and after irradiation, respectively. 2274401400041 Relative detection efficiencies of the HPGe detector 2274401400042 were determined using radioactive sources 56Co, 133Ba, 2274401400043 152Eu, (Firestone and Shirley, 1996; IAEA, 1991), 2274401400044 and the prompt gamma rays from the 14N(n,c)15N 2274401400045 (Miyazaki et al.,2008), and Monte Carlo simulation 2274401400046 code (GEANT4) (Agostinelli et al., 2003). 2274401400047 The uncertainties in the efficiency curve were 2274401400048 evaluated to be within 0.7% at energies between 0.122 2274401400049 and 5 MeV, and 1.0% above 5 MeV. 2274401400050 EN-SEC (E,G) Energy of prompt gamma rays were taken from 2274401400051 Z.Revay,R.B.Firestone,T.Belgya,G.L.Molnar, 2004. Prompt2274401400052 gamma-ray spectrum catalog. In: Molnar, G.L.(Ed.), 2274401400053 Handbook of Prompt Gamma Activation Analysis With 2274401400054 Neutron Beams. Kuwer Academic Publishers, pp.173-364. 2274401400055 CORRECTION For pile-up loses caused by accidental coincidence- 2274401400056 0.38-3.6 %. 2274401400057 The correction for coincidence summing effects was 2274401400058 approximately 5% of the all corrections. 2274401400059 For self-absorption of target material, absorption by 2274401400060 material of target box, and escape ratios. 2274401400061 ERR-ANALYS (ERR-T) Uncertainties were evaluated from the 2274401400062 experimental uncertainties inherent in the counting 2274401400063 statistics, the detection efficiency including total 2274401400064 efficiency for correction of summing effect, the escape2274401400065 ratio, peak evaluation and adopted nuclear data 2274401400066 themselves. 2274401400067 STATUS (TABLE) Table 2 of J,ANE,43,106,2012. 2274401400068 HISTORY (20120821C) M.M 2274401400069 ENDBIB 67 0 2274401400070 NOCOMMON 0 0 2274401400071 DATA 3 8 2274401400072 E DATA ERR-T 2274401400073 KEV PC/REAC PC/REAC 2274401400074 4724.8 2.23 0.05 2274401400075 5067.9 2.18 0.04 2274401400076 5180.9 3.16 0.06 2274401400077 5527.1 6.2 0.1 2274401400078 6929.2 1.86 0.05 2274401400079 7057.9 9.5 0.2 2274401400080 7159.6 4.74 0.08 2274401400081 7243.5 11.2 0.2 2274401400082 ENDDATA 10 0 2274401400083 ENDSUBENT 82 0 2274401499999 SUBENT 22744015 20120821 22332274401500001 BIB 11 72 2274401500002 REACTION (27-CO-59(N,G)27-CO-60,,SPC,,MXW) 2274401500003 Emission probabilities for some intense prompt gamma 2274401500004 rays. 2274401500005 DECAY-DATA (27-CO-60,5.2714YR,DG,1173.237,0.999736) 2274401500006 1173.237+-0.04 keV, 99.9736+-0.0007 % . 2274401500007 REL-REF (R,,R.B.Firestone+,B,FIRESTONE,,1996) 2274401500008 HL, Egamma, intensity were taken from Firestone and 2274401500009 Shirley (1996). 2274401500010 (A,,K.Sudarshan+,J,NIM/A,457,180,2001) 2274401500011 (A,,J.Kopecky+,J,NP/A,427,413,1984) 2274401500012 Z.Revay,R.B.Firestone,T.Belgya,G.L.Molnar, 2004. Prompt2274401500013 gamma-ray spectrum catalog. In: Molnar, G.L.(Ed.), 2274401500014 Handbook of Prompt Gamma Activation Analysis With 2274401500015 Neutron Beams. Kuwer Academic Publishers, pp.173-364. 2274401500016 The values by Z.Revay+,2004 are in agreement with the 2274401500017 present ones within the 10% except for the 5660-keV 2274401500018 gamma ray. 2274401500019 The values by K.Sudarshan+,2001 show agreement with the2274401500020 present ones. 2274401500021 The values by J.Kopecky+,1984 show agreement with the 2274401500022 present ones, nevertheless, their results show a large 2274401500023 deviation below 2000 keV. 2274401500024 INC-SPECT Thermal neutron flux 2.E+7 n/cm**2/sec under 5 MW 2274401500025 operation. 2274401500026 The neutron beam at the irradiation position was 2274401500027 approximately 14x61 mm2. 2274401500028 The fluctuation of neutron flux was monitored by 198Au 2274401500029 activity by inserting the 197Au sample approximately 2274401500030 every 6 h. The fluctuation was determined to be small 2274401500031 enough not to have affected the measurements. 2274401500032 SAMPLE (27-CO-59,NAT=1.00) Natural sample for 59Co. 2274401500033 Metal foil sample were 10x10 mm2. 2274401500034 The samples were located on a holder made of graphite, 2274401500035 and they were set at a 30 deg angle to the detector in 2274401500036 the target box. 2274401500037 59Co abundance 100.%, chemical form Co metal, 2274401500038 thickness 0.1 mm, weight 104.3 mg, 2274401500039 tmp(=ti) 7.8 hr, tmd 180. hr, 2274401500040 tmp - time of prompt gamma measuring, 2274401500041 ti - irradiation time, 2274401500042 tmd - time of beta-delayed gamma-ray measuring. 2274401500043 METHOD (GSPEC) The prompt and beta-delayed gamma-rays were 2274401500044 measured with well calibrated 22% HPGe detector during 2274401500045 irradiation and after irradiation, respectively. 2274401500046 Relative detection efficiencies of the HPGe detector 2274401500047 were determined using radioactive sources 56Co, 133Ba, 2274401500048 152Eu, (Firestone and Shirley, 1996; IAEA, 1991), 2274401500049 and the prompt gamma rays from the 14N(n,c)15N 2274401500050 (Miyazaki et al.,2008), and Monte Carlo simulation 2274401500051 code (GEANT4) (Agostinelli et al., 2003). 2274401500052 The uncertainties in the efficiency curve were 2274401500053 evaluated to be within 0.7% at energies between 0.122 2274401500054 and 5 MeV, and 1.0% above 5 MeV. 2274401500055 EN-SEC (E,G) Energy of prompt gamma rays were taken from 2274401500056 Z.Revay,R.B.Firestone,T.Belgya,G.L.Molnar, 2004. Prompt2274401500057 gamma-ray spectrum catalog. In: Molnar, G.L.(Ed.), 2274401500058 Handbook of Prompt Gamma Activation Analysis With 2274401500059 Neutron Beams. Kuwer Academic Publishers, pp.173-364. 2274401500060 CORRECTION For pile-up loses caused by accidental coincidence- 2274401500061 0.38-3.6 %. 2274401500062 The correction for coincidence summing effects was 2274401500063 approximately 5% of the all corrections. 2274401500064 For self-absorption of target material, absorption by 2274401500065 material of target box, and escape ratios. 2274401500066 ERR-ANALYS (ERR-T) Uncertainties were evaluated from the 2274401500067 experimental uncertainties inherent in the counting 2274401500068 statistics, the detection efficiency including total 2274401500069 efficiency for correction of summing effect, the escape2274401500070 ratio, peak evaluation and adopted nuclear data 2274401500071 themselves. 2274401500072 STATUS (TABLE) Table 2 of J,ANE,43,106,2012. 2274401500073 HISTORY (20120821C) M.M 2274401500074 ENDBIB 72 0 2274401500075 NOCOMMON 0 0 2274401500076 DATA 3 10 2274401500077 E DATA ERR-T 2274401500078 KEV PC/REAC PC/REAC 2274401500079 447.71 8.16 0.13 2274401500080 785.63 5.92 0.08 2274401500081 1515.7 5.16 0.07 2274401500082 1830.8 4.30 0.07 2274401500083 5660.9 7.41 0.12 2274401500084 6706.0 7.35 0.13 2274401500085 6877.2 8.91 0.15 2274401500086 6948.9 0.78 0.03 2274401500087 7055.9 1.81 0.04 2274401500088 7491.5 3.16 0.05 2274401500089 ENDDATA 12 0 2274401500090 ENDSUBENT 89 0 2274401599999 SUBENT 22744016 20120821 22332274401600001 BIB 11 72 2274401600002 REACTION (59-PR-141(N,G)59-PR-142,,SPC,,MXW) 2274401600003 Emission probabilities for some intense prompt gamma 2274401600004 rays. 2274401600005 DECAY-DATA (59-PR-142,19.12HR,DG,1575.6,0.037) 2274401600006 1575.6+-0.5, 3.7+-0.5 %. 2274401600007 REL-REF (R,,R.B.Firestone+,B,FIRESTONE,,1996) 2274401600008 (R,,H.Miyahara,W,MIYAHARA,2005) Private communication. 2274401600009 HL, Egamma were taken from Firestone and Shirley(1996),2274401600010 intensity was taken from Miyahara (2005). 2274401600011 (D,,J.Kern+,J,PR,173,1133,1968) 2274401600012 (A,,T.J.Kennett+,J,CJP,59,1212,1981) 2274401600013 Z.Revay,R.B.Firestone,T.Belgya,G.L.Molnar, 2004. Prompt2274401600014 gamma-ray spectrum catalog. In: Molnar, G.L.(Ed.), 2274401600015 Handbook of Prompt Gamma Activation Analysis With 2274401600016 Neutron Beams. Kuwer Academic Publishers, pp.173-364. 2274401600017 The values by Z.Revay+,2004 are systematically smaller 2274401600018 than the present ones except for the 699-keV gamma-ray.2274401600019 The emission probabilities by J.Kern+,1968 are 2274401600020 systematically larger than the present one. 2274401600021 The values by T.J.Kennett+,1981 are in agreement with 2274401600022 the present results except for the 5140- and 5602-keV 2274401600023 gamma-rays. 2274401600024 INC-SPECT Thermal neutron flux 2.E+7 n/cm**2/sec under 5 MW 2274401600025 operation. 2274401600026 The neutron beam at the irradiation position was 2274401600027 approximately 14x61 mm2. 2274401600028 The fluctuation of neutron flux was monitored by 198Au 2274401600029 activity by inserting the 197Au sample approximately 2274401600030 every 6 h. The fluctuation was determined to be small 2274401600031 enough not to have affected the measurements. 2274401600032 SAMPLE (59-PR-141,NAT=1.00) Natural samples for 141Pr. 2274401600033 Powder samples were wrapped in waxed paper. 2274401600034 The samples were located on a holder made of graphite, 2274401600035 and they were set at a 30 deg angle to the detector in 2274401600036 the target box. 2274401600037 141Pr abundance 100.%, chemical form Pr6O11 powder, 2274401600038 thickness 1.1 mm, weight 71.0 mg, 2274401600039 tmp(=ti) 13.6 hr, tmd 10.7 hr, 2274401600040 tmp - time of prompt gamma measuring, 2274401600041 ti - irradiation time, 2274401600042 tmd - time of beta-delayed gamma-ray measuring. 2274401600043 METHOD (GSPEC) The prompt and beta-delayed gamma-rays were 2274401600044 measured with well calibrated 22% HPGe detector during 2274401600045 irradiation and after irradiation, respectively. 2274401600046 Relative detection efficiencies of the HPGe detector 2274401600047 were determined using radioactive sources 56Co, 133Ba, 2274401600048 152Eu, (Firestone and Shirley, 1996; IAEA, 1991), 2274401600049 and the prompt gamma rays from the 14N(n,c)15N 2274401600050 (Miyazaki et al.,2008), and Monte Carlo simulation 2274401600051 code (GEANT4) (Agostinelli et al., 2003). 2274401600052 The uncertainties in the efficiency curve were 2274401600053 evaluated to be within 0.7% at energies between 0.122 2274401600054 and 5 MeV, and 1.0% above 5 MeV. 2274401600055 EN-SEC (E,G) Energy of prompt gamma rays were taken from 2274401600056 Z.Revay,R.B.Firestone,T.Belgya,G.L.Molnar, 2004. Prompt2274401600057 gamma-ray spectrum catalog. In: Molnar, G.L.(Ed.), 2274401600058 Handbook of Prompt Gamma Activation Analysis With 2274401600059 Neutron Beams. Kuwer Academic Publishers, pp.173-364. 2274401600060 CORRECTION For pile-up loses caused by accidental coincidence- 2274401600061 0.38-3.6 %. 2274401600062 The correction for coincidence summing effects was 2274401600063 approximately 5% of the all corrections. 2274401600064 For self-absorption of target material, absorption by 2274401600065 material of target box, and escape ratios. 2274401600066 ERR-ANALYS (ERR-T) Uncertainties were evaluated from the 2274401600067 experimental uncertainties inherent in the counting 2274401600068 statistics, the detection efficiency including total 2274401600069 efficiency for correction of summing effect, the escape2274401600070 ratio, peak evaluation and adopted nuclear data 2274401600071 themselves. 2274401600072 STATUS (TABLE) Table 2 of J,ANE,43,106,2012. 2274401600073 HISTORY (20120821C) M.M 2274401600074 ENDBIB 72 0 2274401600075 NOCOMMON 0 0 2274401600076 DATA 3 9 2274401600077 E DATA ERR-T 2274401600078 KEV PC/REAC PC/REAC 2274401600079 619.29 1.51 0.04 2274401600080 698.65 1.32 0.04 2274401600081 1006.4 1.49 0.04 2274401600082 1150.9 1.38 0.04 2274401600083 4692.1 2.87 0.07 2274401600084 5140.7 3.51 0.09 2274401600085 5206.0 0.42 0.03 2274401600086 5666.2 3.70 0.08 2274401600087 5843.0 1.57 0.04 2274401600088 ENDDATA 11 0 2274401600089 ENDSUBENT 88 0 2274401699999 SUBENT 22744017 20120821 22332274401700001 BIB 11 69 2274401700002 REACTION (74-W-186(N,G)74-W-187,,SPC,,MXW) 2274401700003 Emission probabilities for some intense prompt gamma 2274401700004 rays. 2274401700005 DECAY-DATA (74-W-187,23.72HR,DG,685.774,0.3269) 2274401700006 685.774+-0.018, 32.69+-0.9 %. 2274401700007 REL-REF (R,,R.B.Firestone+,B,FIRESTONE,,1996) 2274401700008 (R,,N.Marnada+,J,NST,36,1119,1999) 2274401700009 HL, Egamma were taken from Firestone and Shirley(1996),2274401700010 intensity was taken from Marnada+ (1999). 2274401700011 (D,,V.Bondarenko+,J,NP/A,619,1,1997) 2274401700012 (D,,V.Bondarenko+,J,NP/A,811,28,2008) 2274401700013 Z.Revay,R.B.Firestone,T.Belgya,G.L.Molnar, 2004. Prompt2274401700014 gamma-ray spectrum catalog. In: Molnar, G.L.(Ed.), 2274401700015 Handbook of Prompt Gamma Activation Analysis With 2274401700016 Neutron Beams. Kuwer Academic Publishers, pp.173-364. 2274401700017 The values by Z.Revay+,2004 are systematically smaller 2274401700018 than present ones. 2274401700019 The results by V.Bondarenko+,1997,2008 are 2274401700020 systematically smaller than the present results. 2274401700021 INC-SPECT Thermal neutron flux 2.E+7 n/cm**2/sec under 5 MW 2274401700022 operation. 2274401700023 The neutron beam at the irradiation position was 2274401700024 approximately 14x61 mm2. 2274401700025 The fluctuation of neutron flux was monitored by 198Au 2274401700026 activity by inserting the 197Au sample approximately 2274401700027 every 6 h. The fluctuation was determined to be small 2274401700028 enough not to have affected the measurements. 2274401700029 SAMPLE (74-W-186,ENR=0.975) Separated isotope sample for 186W.2274401700030 Powder samples were wrapped in waxed paper. 2274401700031 The samples were located on a holder made of graphite, 2274401700032 and they were set at a 30 deg angle to the detector in 2274401700033 the target box. 2274401700034 186W abundance 97.5%, chemical form WO3 powder, 2274401700035 thickness 1.1 mm, weight 68.8 mg, 2274401700036 tmp(=ti) 8.4 hr, tmd 1.3 hr, 2274401700037 tmp - time of prompt gamma measuring, 2274401700038 ti - irradiation time, 2274401700039 tmd - time of beta-delayed gamma-ray measuring. 2274401700040 METHOD (GSPEC) The prompt and beta-delayed gamma-rays were 2274401700041 measured with well calibrated 22% HPGe detector during 2274401700042 irradiation and after irradiation, respectively. 2274401700043 Relative detection efficiencies of the HPGe detector 2274401700044 were determined using radioactive sources 56Co, 133Ba, 2274401700045 152Eu, (Firestone and Shirley, 1996; IAEA, 1991), 2274401700046 and the prompt gamma rays from the 14N(n,c)15N 2274401700047 (Miyazaki et al.,2008), and Monte Carlo simulation 2274401700048 code (GEANT4) (Agostinelli et al., 2003). 2274401700049 The uncertainties in the efficiency curve were 2274401700050 evaluated to be within 0.7% at energies between 0.122 2274401700051 and 5 MeV, and 1.0% above 5 MeV. 2274401700052 EN-SEC (E,G) Energy of prompt gamma rays were taken from 2274401700053 Z.Revay,R.B.Firestone,T.Belgya,G.L.Molnar, 2004. Prompt2274401700054 gamma-ray spectrum catalog. In: Molnar, G.L.(Ed.), 2274401700055 Handbook of Prompt Gamma Activation Analysis With 2274401700056 Neutron Beams. Kuwer Academic Publishers, pp.173-364. 2274401700057 CORRECTION For pile-up loses caused by accidental coincidence- 2274401700058 0.38-3.6 %. 2274401700059 The correction for coincidence summing effects was 2274401700060 approximately 5% of the all corrections. 2274401700061 For self-absorption of target material, absorption by 2274401700062 material of target box, and escape ratios. 2274401700063 ERR-ANALYS (ERR-T) Uncertainties were evaluated from the 2274401700064 experimental uncertainties inherent in the counting 2274401700065 statistics, the detection efficiency including total 2274401700066 efficiency for correction of summing effect, the escape2274401700067 ratio, peak evaluation and adopted nuclear data 2274401700068 themselves. 2274401700069 STATUS (TABLE) Table 2 of J,ANE,43,106,2012. 2274401700070 HISTORY (20120821C) M.M 2274401700071 ENDBIB 69 0 2274401700072 NOCOMMON 0 0 2274401700073 DATA 3 11 2274401700074 E DATA ERR-T 2274401700075 KEV PC/REAC PC/REAC 2274401700076 145.79 12.77 0.17 2274401700077 201.44 4.09 0.06 2274401700078 204.83 1.81 0.03 2274401700079 273.10 3.58 0.05 2274401700080 577.30 2.60 0.04 2274401700081 3469.4 1.53 0.04 2274401700082 4574.9 0.94 0.04 2274401700083 4626.4 1.83 0.05 2274401700084 4684.8 2.21 0.05 2274401700085 5261.7 6.62 0.11 2274401700086 5320.7 4.58 0.08 2274401700087 ENDDATA 13 0 2274401700088 ENDSUBENT 87 0 2274401799999 SUBENT 22744018 20120821 22332274401800001 BIB 12 69 2274401800002 REACTION (79-AU-197(N,G)79-AU-198,,SPC,,MXW) 2274401800003 Emission probabilities for some intense prompt gamma 2274401800004 rays. 2274401800005 DECAY-DATA (79-AU-198,2.695D,DG,411.80205,0.9858) 2274401800006 411.80205+-0.00017, 98.58+-0.12 %. 2274401800007 REL-REF (R,,R.B.Firestone+,B,FIRESTONE,,1996) 2274401800008 HL, Egamma, intensity were taken from Firestone and 2274401800009 Shirley (1996). 2274401800010 (D,,U.Mayerhofer+,J,FIZ/B,5,229,1996) 2274401800011 Z.Revay,R.B.Firestone,T.Belgya,G.L.Molnar, 2004. Prompt2274401800012 gamma-ray spectrum catalog. In: Molnar, G.L.(Ed.), 2274401800013 Handbook of Prompt Gamma Activation Analysis With 2274401800014 Neutron Beams. Kuwer Academic Publishers, pp.173-364. 2274401800015 The values by Z.Revay+,2004 are generally in 2274401800016 agreement with the present ones. 2274401800017 The disagreement with U.Mayerhofer+,1996. 2274401800018 INC-SPECT Thermal neutron flux 2.E+7 n/cm**2/sec under 5 MW 2274401800019 operation. 2274401800020 The neutron beam at the irradiation position was 2274401800021 approximately 14x61 mm2. 2274401800022 The fluctuation of neutron flux was monitored by 198Au 2274401800023 activity by inserting the 197Au sample approximately 2274401800024 every 6 h. The fluctuation was determined to be small 2274401800025 enough not to have affected the measurements. 2274401800026 SAMPLE (79-AU-197,NAT=1.00) Natural sample for 197Au. 2274401800027 Metal foil samples were 10x10 mm2. 2274401800028 The samples were located on a holder made of graphite, 2274401800029 and they were set at a 30 deg angle to the detector in 2274401800030 the target box. 2274401800031 197Au abundance 100.%, chemical form Au metal, 2274401800032 thickness 0.05 mm, weight 18.4 mg, 2274401800033 tmp(=ti) 13.9 hr, tmd 0.5 hr, 2274401800034 tmp - time of prompt gamma measuring, 2274401800035 ti - irradiation time, 2274401800036 tmd - time of beta-delayed gamma-ray measuring. 2274401800037 METHOD (GSPEC) The prompt and beta-delayed gamma-rays were 2274401800038 measured with well calibrated 22% HPGe detector during 2274401800039 irradiation and after irradiation, respectively. 2274401800040 Relative detection efficiencies of the HPGe detector 2274401800041 were determined using radioactive sources 56Co, 133Ba, 2274401800042 152Eu, (Firestone and Shirley, 1996; IAEA, 1991), 2274401800043 and the prompt gamma rays from the 14N(n,c)15N 2274401800044 (Miyazaki et al.,2008), and Monte Carlo simulation 2274401800045 code (GEANT4) (Agostinelli et al., 2003). 2274401800046 The uncertainties in the efficiency curve were 2274401800047 evaluated to be within 0.7% at energies between 0.122 2274401800048 and 5 MeV, and 1.0% above 5 MeV. 2274401800049 EN-SEC (E,G) Energy of prompt gamma rays were taken from 2274401800050 Z.Revay,R.B.Firestone,T.Belgya,G.L.Molnar, 2004. Prompt2274401800051 gamma-ray spectrum catalog. In: Molnar, G.L.(Ed.), 2274401800052 Handbook of Prompt Gamma Activation Analysis With 2274401800053 Neutron Beams. Kuwer Academic Publishers, pp.173-364. 2274401800054 CORRECTION For pile-up loses caused by accidental coincidence- 2274401800055 0.38-3.6 %. 2274401800056 The correction for coincidence summing effects was 2274401800057 approximately 5% of the all corrections. 2274401800058 For self-absorption of target material, absorption by 2274401800059 material of target box, and escape ratios. 2274401800060 FLAG (1.) Treated as singlet of the 2274401800061 168.334 + 170.103 + 170.399 keV gamma-ray in 2274401800062 Z.Revay+(2004) - see EN-SEC. 2274401800063 ERR-ANALYS (ERR-T) Uncertainties were evaluated from the 2274401800064 experimental uncertainties inherent in the counting 2274401800065 statistics, the detection efficiency including total 2274401800066 efficiency for correction of summing effect, the escape2274401800067 ratio, peak evaluation and adopted nuclear data 2274401800068 themselves. 2274401800069 STATUS (TABLE) Table 2 of J,ANE,43,106,2012. 2274401800070 HISTORY (20120821C) M.M 2274401800071 ENDBIB 69 0 2274401800072 NOCOMMON 0 0 2274401800073 DATA 4 11 2274401800074 E DATA ERR-T FLAG 2274401800075 KEV PC/REAC PC/REAC NO-DIM 2274401800076 168.33 4.97 0.07 1. 2274401800077 192.39 4.10 0.06 2274401800078 214.97 7.04 0.10 2274401800079 236.05 3.86 0.05 2274401800080 247.57 5.25 0.07 2274401800081 261.40 5.88 0.08 2274401800082 5710.5 1.43 0.09 2274401800083 6252.1 5.18 0.09 2274401800084 6319.3 2.80 0.05 2274401800085 6457.0 1.92 0.04 2274401800086 6512.3 1.37 0.03 2274401800087 ENDDATA 13 0 2274401800088 ENDSUBENT 87 0 2274401899999 ENDENTRY 18 0 2274499999999