ENTRY 31495 20160929 31753149500000001 SUBENT 31495001 20160929 31753149500100001 BIB 12 38 3149500100002 TITLE Excitation functions of some (n,p) and (n,alpha) 3149500100003 reactions from threshold to 16 MeV 3149500100004 AUTHOR (R.Doczi, V.Semkova, A.Fenyvesi, N.Yamamuro, 3149500100005 Cs.M.Buczko, J.Csikai) 3149500100006 INSTITUTE (3HUNKOS,3BULBLA,3HUNDEB) 3149500100007 (2JPNJPN) Kitahassaku 60, Midori-ku, Yokohama, Kanagawa3149500100008 REFERENCE (J,NSE,129,164,1998) 3149500100009 SAMPLE High-purity (Goodfellow) natural metal samples, disk- 3149500100010 shaped (19 mm diam.) with thickness between 0.25 and 3149500100011 1 mm, and rectangular (10x15 mm) shaped. 3149500100012 METHOD (ACTIV) 3149500100013 DETECTOR (GELI,HPGE) Absolute activity measurements. 3149500100014 MONITOR (13-AL-27(N,A)11-NA-24,,SIG) 3149500100015 DECAY-MON (11-NA-24,14.659HR,DG,1368.598,1.) 3149500100016 CORRECTION Corrections were made for the following effects: 3149500100017 - true coincidence 3149500100018 - gamma-ray self-absorption 3149500100019 - dead time 3149500100020 - contribution of low-energy breakup neutrons to the 3149500100021 activation. Therefore the spectral shape of the 3149500100022 neutrons produced in the H-2(d,n)He-3 reaction was 3149500100023 determined by activation and pulse-height unfolding 3149500100024 methods. 3149500100025 ERR-ANALYS (ERR-T) Errors are from the following sources: 3149500100026 - counting statistics 3149500100027 - sample mass 3149500100028 - energy and fluence uncertainties 3149500100029 - decay constants 3149500100030 - effect of low-energy neutrons 3149500100031 - reference cross sections 3149500100032 - detector efficiency 3149500100033 HISTORY (19980714C) HW. 3149500100034 (20020307U) OS. STATUS text corrected, changed to 3149500100035 4-digit year. 3149500100036 (20130625U) On. AUTHOR: .CS.M.BUCZKO -> Cs.M.Buczko 3149500100037 (20150508U) VS. REL-REF added to the article and the 3149500100038 Entry with incident neutron flux energy distribution 3149500100039 (20160922U) VS. DECAY-DATA corrected in 010. 3149500100040 ENDBIB 38 0 3149500100041 NOCOMMON 0 0 3149500100042 ENDSUBENT 41 0 3149500199999 SUBENT 31495002 20020307 00003149500200001 BIB 5 8 3149500200002 REACTION (21-SC-45(N,A)19-K-42,,SIG) 3149500200003 FACILITY (CYCLO,3HUNDEB) ATOMKI variable energy cyclotron. 3149500200004 INC-SOURCE (D-D) Neutrons in the 7- to 12.5 MeV energy range were 3149500200005 produced by bombarding a D2 gas target with variable 3149500200006 energy deuterons. 3149500200007 DECAY-DATA (19-K-42,12.360HR,DG,1524.58,.188) 3149500200008 STATUS Data are taken from table 3 of Nuclear Science and 3149500200009 Engineering, vol. 129, pp. 164-174 (1998). 3149500200010 ENDBIB 8 0 3149500200011 NOCOMMON 0 0 3149500200012 DATA 4 1 3149500200013 EN EN-ERR DATA ERR-T 3149500200014 MEV MEV MB MB 3149500200015 11.34 0.22 45.6 2.3 3149500200016 ENDDATA 3 0 3149500200017 ENDSUBENT 16 0 3149500299999 SUBENT 31495003 20020307 00003149500300001 BIB 5 10 3149500300002 REACTION (23-V-51(N,A)21-SC-48,,SIG) 3149500300003 FACILITY (CYCLO,3HUNDEB) ATOMKI variable energy cyclotron. 3149500300004 INC-SOURCE (D-D) Neutrons in the 7- to 12.5 MeV energy range were 3149500300005 produced by bombarding a D2 gas target with variable 3149500300006 energy deuterons. 3149500300007 DECAY-DATA (21-SC-48,1.821D,DG,983.501,1., 3149500300008 DG,1037.4961,.975, 3149500300009 DG,1312.046,1.) 3149500300010 STATUS Data are taken from table 3 of Nuclear Science and 3149500300011 Engineering, vol. 129, pp. 164-174 (1998). 3149500300012 ENDBIB 10 0 3149500300013 NOCOMMON 0 0 3149500300014 DATA 4 4 3149500300015 EN EN-ERR DATA ERR-T 3149500300016 MEV MEV MB MB 3149500300017 9.92 0.19 4.25 0.21 3149500300018 11.19 0.20 7.15 0.36 3149500300019 11.34 0.22 7.02 0.84 3149500300020 12.53 0.25 10.7 0.6 3149500300021 ENDDATA 6 0 3149500300022 ENDSUBENT 21 0 3149500399999 SUBENT 31495004 20020307 00003149500400001 BIB 5 8 3149500400002 REACTION (27-CO-59(N,A)25-MN-56,,SIG) 3149500400003 FACILITY (CYCLO,3HUNDEB) ATOMKI variable energy cyclotron. 3149500400004 INC-SOURCE (D-D) Neutrons in the 7- to 12.5 MeV energy range were 3149500400005 produced by bombarding a D2 gas target with variable 3149500400006 energy deuterons. 3149500400007 DECAY-DATA (25-MN-56,2.5785HR,DG,846.812,.989) 3149500400008 STATUS Data are taken from table 3 of Nuclear Science and 3149500400009 Engineering, vol. 129, pp. 164-174 (1998). 3149500400010 ENDBIB 8 0 3149500400011 NOCOMMON 0 0 3149500400012 DATA 4 1 3149500400013 EN EN-ERR DATA ERR-T 3149500400014 MEV MEV MB MB 3149500400015 11.34 0.22 27.7 1.4 3149500400016 ENDDATA 3 0 3149500400017 ENDSUBENT 16 0 3149500499999 SUBENT 31495005 20020307 00003149500500001 BIB 5 8 3149500500002 REACTION (40-ZR-90(N,A)38-SR-87-M,,SIG) 3149500500003 FACILITY (CYCLO,3HUNDEB) ATOMKI variable energy cyclotron. 3149500500004 INC-SOURCE (D-D) Neutrons in the 7- to 12.5 MeV energy range were 3149500500005 produced by bombarding a D2 gas target with variable 3149500500006 energy deuterons. 3149500500007 DECAY-DATA (38-SR-87-M,2.795HR,DG,388.40,.823) 3149500500008 STATUS Data are taken from table 3 of Nuclear Science and 3149500500009 Engineering, vol. 129, pp. 164-174 (1998). 3149500500010 ENDBIB 8 0 3149500500011 NOCOMMON 0 0 3149500500012 DATA 4 4 3149500500013 EN EN-ERR DATA ERR-T 3149500500014 MEV MEV MB MB 3149500500015 9.92 0.19 0.63 .04 3149500500016 11.19 0.20 1.63 0.12 3149500500017 11.34 0.22 2.06 0.20 3149500500018 12.53 0.25 2.33 0.18 3149500500019 ENDDATA 6 0 3149500500020 ENDSUBENT 19 0 3149500599999 SUBENT 31495006 20020307 00003149500600001 BIB 5 10 3149500600002 REACTION (40-ZR-94(N,A)38-SR-91,,SIG) 3149500600003 FACILITY (CYCLO,3HUNDEB) ATOMKI variable energy cyclotron. 3149500600004 INC-SOURCE (D-D) Neutrons in the 7- to 12.5 MeV energy range were 3149500600005 produced by bombarding a D2 gas target with variable 3149500600006 energy deuterons. 3149500600007 DECAY-DATA (38-SR-91,9.52HR,DG,555.56,.615, 3149500600008 DG,749.72,.236, 3149500600009 DG,1024.28,.33) 3149500600010 STATUS Data are taken from table 3 of Nuclear Science and 3149500600011 Engineering, vol. 129, pp. 164-174 (1998). 3149500600012 ENDBIB 10 0 3149500600013 NOCOMMON 0 0 3149500600014 DATA 4 2 3149500600015 EN EN-ERR DATA ERR-T 3149500600016 MEV MEV MB MB 3149500600017 11.34 0.22 1.77 .09 3149500600018 12.53 0.25 2.35 .21 3149500600019 ENDDATA 4 0 3149500600020 ENDSUBENT 19 0 3149500699999 SUBENT 31495007 20020307 00003149500700001 BIB 5 8 3149500700002 REACTION (42-MO-92(N,A)40-ZR-89,,SIG) 3149500700003 FACILITY (CYCLO,3HUNDEB) ATOMKI variable energy cyclotron. 3149500700004 INC-SOURCE (D-D) Neutrons in the 7- to 12.5 MeV energy range were 3149500700005 produced by bombarding a D2 gas target with variable 3149500700006 energy deuterons. 3149500700007 DECAY-DATA (40-ZR-89-G,3.268D,DG,909.15,.9901) 3149500700008 STATUS Data are taken from table 3 of Nuclear Science and 3149500700009 Engineering, vol. 129, pp. 164-174 (1998). 3149500700010 ENDBIB 8 0 3149500700011 NOCOMMON 0 0 3149500700012 DATA 4 5 3149500700013 EN EN-ERR DATA ERR-T 3149500700014 MEV MEV MB MB 3149500700015 8.97 0.18 7.97 0.7 3149500700016 10.3 0.20 12.1 0.8 3149500700017 11.19 0.22 13.1 1.1 3149500700018 11.34 0.29 13.8 1.1 3149500700019 12.53 0.30 19.7 1.5 3149500700020 ENDDATA 7 0 3149500700021 ENDSUBENT 20 0 3149500799999 SUBENT 31495008 20020307 00003149500800001 BIB 5 9 3149500800002 REACTION (41-NB-93(N,A)39-Y-90-M,,SIG) 3149500800003 FACILITY (CYCLO,3HUNDEB) ATOMKI variable energy cyclotron. 3149500800004 INC-SOURCE (D-D) Neutrons in the 7- to 12.5 MeV energy range were 3149500800005 produced by bombarding a D2 gas target with variable 3149500800006 energy deuterons. 3149500800007 DECAY-DATA (39-Y-90-M,3.19HR,DG,202.47,.966, 3149500800008 DG,479.49,.91) 3149500800009 STATUS Data are taken from table 3 of Nuclear Science and 3149500800010 Engineering, vol. 129, pp. 164-174 (1998). 3149500800011 ENDBIB 9 0 3149500800012 NOCOMMON 0 0 3149500800013 DATA 4 1 3149500800014 EN EN-ERR DATA ERR-T 3149500800015 MEV MEV MB MB 3149500800016 11.34 0.22 3.56 0.18 3149500800017 ENDDATA 3 0 3149500800018 ENDSUBENT 17 0 3149500899999 SUBENT 31495009 20020307 00003149500900001 BIB 5 9 3149500900002 REACTION (40-ZR-90(N,P)39-Y-90-M,,SIG) 3149500900003 FACILITY (CYCLO,3HUNDEB) ATOMKI variable energy cyclotron. 3149500900004 INC-SOURCE (D-D) Neutrons in the 7- to 12.5 MeV energy range were 3149500900005 produced by bombarding a D2 gas target with variable 3149500900006 energy deuterons. 3149500900007 DECAY-DATA (39-Y-90-M,3.19HR,DG,202.47,.966, 3149500900008 DG,479.49,.91) 3149500900009 STATUS Data are taken from table 3 of Nuclear Science and 3149500900010 Engineering, vol. 129, pp. 164-174 (1998). 3149500900011 ENDBIB 9 0 3149500900012 NOCOMMON 0 0 3149500900013 DATA 4 5 3149500900014 EN EN-ERR DATA ERR-T 3149500900015 MEV MEV MB MB 3149500900016 7.16 0.17 1.09 0.05 3149500900017 9.92 0.19 2.70 0.27 3149500900018 11.19 0.20 4.88 0.24 3149500900019 11.34 0.22 6.59 0.5 3149500900020 12.53 0.25 7.91 0.39 3149500900021 ENDDATA 7 0 3149500900022 ENDSUBENT 21 0 3149500999999 SUBENT 31495010 20160929 31753149501000001 BIB 6 9 3149501000002 REACTION (40-ZR-91(N,P)39-Y-91-M,,SIG) 3149501000003 FACILITY (CYCLO,3HUNDEB) ATOMKI variable energy cyclotron. 3149501000004 INC-SOURCE (D-D) Neutrons in the 7- to 12.5 MeV energy range were 3149501000005 produced by bombarding a D2 gas target with variable 3149501000006 energy deuterons. 3149501000007 DECAY-DATA (39-Y-91-M,49.71MIN,DG,555.56,.9490) 3149501000008 STATUS (TABLE) Data are taken from table 3 of Nuclear Science 3149501000009 and Engineering, vol. 129, pp. 164-174 (1998). 3149501000010 HISTORY (20160922U) VS. DECAY-DATA corrected. 3149501000011 ENDBIB 9 0 3149501000012 NOCOMMON 0 0 3149501000013 DATA 4 4 3149501000014 EN EN-ERR DATA ERR-T 3149501000015 MEV MEV MB MB 3149501000016 7.16 0.17 1.68 0.2 3149501000017 9.92 0.19 4.15 0.5 3149501000018 11.34 0.22 9.6 0.5 3149501000019 12.53 0.25 11.0 1.0 3149501000020 ENDDATA 6 0 3149501000021 ENDSUBENT 20 0 3149501099999 SUBENT 31495011 20020307 00003149501100001 BIB 5 8 3149501100002 REACTION (40-ZR-92(N,P)39-Y-92,,SIG) 3149501100003 FACILITY (CYCLO,3HUNDEB) ATOMKI variable energy cyclotron. 3149501100004 INC-SOURCE (D-D) Neutrons in the 7- to 12.5 MeV energy range were 3149501100005 produced by bombarding a D2 gas target with variable 3149501100006 energy deuterons. 3149501100007 DECAY-DATA (39-Y-92,3.54HR,DG,934.53,.139) 3149501100008 STATUS Data are taken from table 3 of Nuclear Science and 3149501100009 Engineering, vol. 129, pp. 164-174 (1998). 3149501100010 ENDBIB 8 0 3149501100011 NOCOMMON 0 0 3149501100012 DATA 4 1 3149501100013 EN EN-ERR DATA ERR-T 3149501100014 MEV MEV MB MB 3149501100015 11.34 0.22 7.5 0.4 3149501100016 ENDDATA 3 0 3149501100017 ENDSUBENT 16 0 3149501199999 SUBENT 31495012 20020307 00003149501200001 BIB 5 8 3149501200002 REACTION (42-MO-92(N,P)41-NB-92-M,,SIG) 3149501200003 FACILITY (CYCLO,3HUNDEB) ATOMKI variable energy cyclotron. 3149501200004 INC-SOURCE (D-D) Neutrons in the 7- to 12.5 MeV energy range were 3149501200005 produced by bombarding a D2 gas target with variable 3149501200006 energy deuterons. 3149501200007 DECAY-DATA (41-NB-92-M,10.15D,DG,934.53,.99) 3149501200008 STATUS Data are taken from table 3 of Nuclear Science and 3149501200009 Engineering, vol. 129, pp. 164-174 (1998). 3149501200010 ENDBIB 8 0 3149501200011 NOCOMMON 0 0 3149501200012 DATA 4 4 3149501200013 EN EN-ERR DATA ERR-T 3149501200014 MEV MEV MB MB 3149501200015 8.97 0.18 114. 9. 3149501200016 10.3 0.20 116. 6. 3149501200017 11.19 0.22 113. 7. 3149501200018 12.53 0.30 112. 7. 3149501200019 ENDDATA 6 0 3149501200020 ENDSUBENT 19 0 3149501299999 SUBENT 31495013 20020307 00003149501300001 BIB 5 11 3149501300002 REACTION (42-MO-96(N,P)41-NB-96,,SIG) 3149501300003 FACILITY (CYCLO,3HUNDEB) ATOMKI variable energy cyclotron. 3149501300004 INC-SOURCE (D-D) Neutrons in the 7- to 12.5 MeV energy range were 3149501300005 produced by bombarding a D2 gas target with variable 3149501300006 energy deuterons. 3149501300007 DECAY-DATA (41-NB-96,23.35HR,DG,460.01,.285, 3149501300008 DG,568.86,.568, 3149501300009 DG,778.196,.9688, 3149501300010 DG,1091.316,.485) 3149501300011 STATUS Data are taken from table 3 of Nuclear Science and 3149501300012 Engineering, vol. 129, pp. 164-174 (1998). 3149501300013 ENDBIB 11 0 3149501300014 NOCOMMON 0 0 3149501300015 DATA 4 3 3149501300016 EN EN-ERR DATA ERR-T 3149501300017 MEV MEV MB MB 3149501300018 11.19 0.22 8.4 0.8 3149501300019 11.34 0.29 8.5 0.9 3149501300020 12.53 0.30 15.9 1.5 3149501300021 ENDDATA 5 0 3149501300022 ENDSUBENT 21 0 3149501399999 SUBENT 31495014 20020307 00003149501400001 BIB 5 8 3149501400002 REACTION (42-MO-97(N,P)41-NB-97,,SIG) 3149501400003 FACILITY (CYCLO,3HUNDEB) ATOMKI variable energy cyclotron. 3149501400004 INC-SOURCE (D-D) Neutrons in the 7- to 12.5 MeV energy range were 3149501400005 produced by bombarding a D2 gas target with variable 3149501400006 energy deuterons. 3149501400007 DECAY-DATA (41-NB-97-G,1.202HR,DG,658.22,.9834) 3149501400008 STATUS Data are taken from table 3 of Nuclear Science and 3149501400009 Engineering, vol. 129, pp. 164-174 (1998). 3149501400010 ENDBIB 8 0 3149501400011 NOCOMMON 0 0 3149501400012 DATA 4 3 3149501400013 EN EN-ERR DATA ERR-T 3149501400014 MEV MEV MB MB 3149501400015 8.97 0.18 0.91 0.10 3149501400016 10.30 0.20 2.7 0.2 3149501400017 12.53 0.30 9.5 0.9 3149501400018 ENDDATA 5 0 3149501400019 ENDSUBENT 18 0 3149501499999 SUBENT 31495015 20020307 00003149501500001 BIB 5 11 3149501500002 REACTION (28-NI-60(N,P)27-CO-60,,SIG) 3149501500003 INC-SOURCE (D-T) Neutrons were produced by bombarding a thick TiT 3149501500004 target, in a scatter-free arrangement, with a 3149501500005 180 +- 5 keV deuteron beam. The neutron energy was 3149501500006 selected by the angular position of the sample with 3149501500007 respect to the deuteron beam axis. 3149501500008 DECAY-DATA (27-CO-60-G,5.271YR,DG,1173.231,.999, 3149501500009 DG,1332.501,.999824) 3149501500010 STATUS Data are taken from table 3 of Nuclear Science and 3149501500011 Engineering, vol. 129, pp. 164-174 (1998). 3149501500012 HISTORY (20020307A) OS.- Numerical values corrected. 3149501500013 ENDBIB 11 0 3149501500014 NOCOMMON 0 0 3149501500015 DATA 4 3 3149501500016 EN EN-ERR DATA ERR-T 3149501500017 MEV MEV MB MB 3149501500018 13.82 0.08 164.2 8.5 3149501500019 14.099 0.07 151.0 7.6 3149501500020 14.67 0.135 140.6 7.3 3149501500021 ENDDATA 5 0 3149501500022 ENDSUBENT 21 0 3149501599999 SUBENT 31495016 20150508 31703149501600001 BIB 8 21 3149501600002 REACTION (26-FE-54(N,A)24-CR-51,,SIG,,SPA) 3149501600003 INC-SOURCE (D-BE) Neutrons were produced by bombarding a 3 mm 3149501600004 thick Be target with 9.72 MeV deuterons. 3149501600005 INC-SPECT The volume-averaged flux density spectra of the neu- 3149501600006 trons was determined via the multiple foil activation 3149501600007 technique and spectrum unfolding. The average energy 3149501600008 is 4.3 MeV ( J.Csikai, private communication). 3149501600009 Incident neutron flux energy distribution in 3149501600010 Subentry D0055002. 3149501600011 REL-REF (N,D0055002,L.Olah+,J,NIM/A,404,373,1998) Incident 3149501600012 neutron flux energy distribution. 3149501600013 METHOD (STTA) Stacks of high-purity Fe,V,Co,Zn,Zr,Nb,Mo,Ni,Al,3149501600014 Sc and Ti foils with a set of Al,In,Fe,Ti,Au,Nb,Ni and 3149501600015 Zr foils as threshold detectors. Alluminium foils 3149501600016 placed at different positions within the stack were 3149501600017 applied to estimate the neutron flux attenuation in 3149501600018 the stack. 3149501600019 DECAY-DATA (24-CR-51,27.704D,DG,320.084,.0983) 3149501600020 STATUS (TABLE) Data are taken from table 4 of Nuclear Science 3149501600021 and Engineering, vol. 129, pp. 164-174 (1998). 3149501600022 HISTORY (20150508U) VS. REL-REF added. INC-SPECT inf. added. 3149501600023 ENDBIB 21 0 3149501600024 COMMON 1 3 3149501600025 EN-MEAN 3149501600026 MEV 3149501600027 4.3 3149501600028 ENDCOMMON 3 0 3149501600029 DATA 2 1 3149501600030 DATA ERR-T 3149501600031 MB MB 3149501600032 7.80 .80 3149501600033 ENDDATA 3 0 3149501600034 ENDSUBENT 33 0 3149501699999 SUBENT 31495017 20150508 31703149501700001 BIB 8 23 3149501700002 REACTION (23-V-51(N,A)21-SC-48,,SIG,,SPA) 3149501700003 INC-SOURCE (D-BE) Neutrons were produced by bombarding a 3 mm 3149501700004 thick Be target with 9.72 MeV deuterons. 3149501700005 INC-SPECT The volume-averaged flux density spectra of the neu- 3149501700006 trons was determined via the multiple foil activation 3149501700007 technique and spectrum unfolding. The average energy 3149501700008 is 4.3 MeV ( J.Csikai, private communication) 3149501700009 Incident neutron flux energy distribution in 3149501700010 Subentry D0055002. 3149501700011 REL-REF (N,D0055002,L.Olah+,J,NIM/A,404,373,1998) Incident 3149501700012 neutron flux energy distribution. 3149501700013 METHOD (STTA) Stacks of high-purity Fe,V,Co,Zn,Zr,Nb,Mo,Ni,Al,3149501700014 Sc and Ti foils with a set of Al,In,Fe,Ti,Au,Nb,Ni and 3149501700015 Zr foils as threshold detectors. Alluminium foils 3149501700016 placed at different positions within the stack were 3149501700017 applied to estimate the neutron flux attenuation in 3149501700018 the stack. 3149501700019 DECAY-DATA (21-SC-48,1.821D,DG,983.501,1., 3149501700020 DG,1037.4961,.975, 3149501700021 DG,1312.046,1.) 3149501700022 STATUS (TABLE) Data are taken from table 4 of Nuclear Science 3149501700023 and Engineering, vol. 129, pp. 164-174 (1998). 3149501700024 HISTORY (20150508U) VS. REL-REF added. INC-SPECT inf. added. 3149501700025 ENDBIB 23 0 3149501700026 COMMON 1 3 3149501700027 EN-MEAN 3149501700028 MEV 3149501700029 4.3 3149501700030 ENDCOMMON 3 0 3149501700031 DATA 2 1 3149501700032 DATA ERR-T 3149501700033 MB MB 3149501700034 .61 .06 3149501700035 ENDDATA 3 0 3149501700036 ENDSUBENT 35 0 3149501799999 SUBENT 31495018 20150508 31703149501800001 BIB 8 21 3149501800002 REACTION (27-CO-59(N,A)25-MN-56,,SIG,,SPA) 3149501800003 INC-SOURCE (D-BE) Neutrons were produced by bombarding a 3 mm 3149501800004 thick Be target with 9.72 MeV deuterons. 3149501800005 INC-SPECT The volume-averaged flux density spectra of the neu- 3149501800006 trons was determined via the multiple foil activation 3149501800007 technique and spectrum unfolding. The average energy 3149501800008 is 4.3 MeV ( J.Csikai, private communication) 3149501800009 Incident neutron flux energy distribution in 3149501800010 Subentry D0055002. 3149501800011 REL-REF (N,D0055002,L.Olah+,J,NIM/A,404,373,1998) Incident 3149501800012 neutron flux energy distribution. 3149501800013 METHOD (STTA) Stacks of high-purity Fe,V,Co,Zn,Zr,Nb,Mo,Ni,Al,3149501800014 Sc and Ti foils with a set of Al,In,Fe,Ti,Au,Nb,Ni and 3149501800015 Zr foils as threshold detectors. Alluminium foils 3149501800016 placed at different positions within the stack were 3149501800017 applied to estimate the neutron flux attenuation in 3149501800018 the stack. 3149501800019 DECAY-DATA (25-MN-56,2.5785HR,DG,846.812,.989) 3149501800020 STATUS (TABLE) Data are taken from table 4 of Nuclear Science 3149501800021 and Engineering, vol. 129, pp. 164-174 (1998). 3149501800022 HISTORY (20150508U) VS. REL-REF added. INC-SPECT inf. added. 3149501800023 ENDBIB 21 0 3149501800024 COMMON 1 3 3149501800025 EN-MEAN 3149501800026 MEV 3149501800027 4.3 3149501800028 ENDCOMMON 3 0 3149501800029 DATA 2 1 3149501800030 DATA ERR-T 3149501800031 MB MB 3149501800032 2.10 0.18 3149501800033 ENDDATA 3 0 3149501800034 ENDSUBENT 33 0 3149501899999 SUBENT 31495019 20150508 31703149501900001 BIB 8 22 3149501900002 REACTION (30-ZN-68(N,A)28-NI-65,,SIG,,SPA) 3149501900003 INC-SOURCE (D-BE) Neutrons were produced by bombarding a 3 mm 3149501900004 thick Be target with 9.72 MeV deuterons. 3149501900005 INC-SPECT The volume-averaged flux density spectra of the neu- 3149501900006 trons was determined via the multiple foil activation 3149501900007 technique and spectrum unfolding. The average energy 3149501900008 is 4.3 MeV ( J.Csikai, private communication) 3149501900009 Incident neutron flux energy distribution in 3149501900010 Subentry D0055002. 3149501900011 REL-REF (N,D0055002,L.Olah+,J,NIM/A,404,373,1998) Incident 3149501900012 neutron flux energy distribution. 3149501900013 METHOD (STTA) Stacks of high-purity Fe,V,Co,Zn,Zr,Nb,Mo,Ni,Al,3149501900014 Sc and Ti foils with a set of Al,In,Fe,Ti,Au,Nb,Ni and 3149501900015 Zr foils as threshold detectors. Alluminium foils 3149501900016 placed at different positions within the stack were 3149501900017 applied to estimate the neutron flux attenuation in 3149501900018 the stack. 3149501900019 DECAY-DATA (28-NI-65,2.520HR,DG,1115.584,.148, 3149501900020 DG,1481.90,.235) 3149501900021 STATUS (TABLE) Data are taken from table 4 of Nuclear Science 3149501900022 and Engineering, vol. 129, pp. 164-174 (1998). 3149501900023 HISTORY (20150508U) VS. REL-REF added. INC-SPECT inf. added. 3149501900024 ENDBIB 22 0 3149501900025 COMMON 1 3 3149501900026 EN-MEAN 3149501900027 MEV 3149501900028 4.3 3149501900029 ENDCOMMON 3 0 3149501900030 DATA 2 1 3149501900031 DATA ERR-T 3149501900032 MB MB 3149501900033 .67 .07 3149501900034 ENDDATA 3 0 3149501900035 ENDSUBENT 34 0 3149501999999 SUBENT 31495020 20150508 31703149502000001 BIB 8 21 3149502000002 REACTION (40-ZR-90(N,A)38-SR-87-M,,SIG,,SPA) 3149502000003 INC-SOURCE (D-BE) Neutrons were produced by bombarding a 3 mm 3149502000004 thick Be target with 9.72 MeV deuterons. 3149502000005 INC-SPECT The volume-averaged flux density spectra of the neu- 3149502000006 trons was determined via the multiple foil activation 3149502000007 technique and spectrum unfolding. The average energy 3149502000008 is 4.3 MeV ( J.Csikai, private communication) 3149502000009 Incident neutron flux energy distribution in 3149502000010 Subentry D0055002. 3149502000011 REL-REF (N,D0055002,L.Olah+,J,NIM/A,404,373,1998) Incident 3149502000012 neutron flux energy distribution. 3149502000013 METHOD (STTA) Stacks of high-purity Fe,V,Co,Zn,Zr,Nb,Mo,Ni,Al,3149502000014 Sc and Ti foils with a set of Al,In,Fe,Ti,Au,Nb,Ni and 3149502000015 Zr foils as threshold detectors. Alluminium foils 3149502000016 placed at different positions within the stack were 3149502000017 applied to estimate the neutron flux attenuation in 3149502000018 the stack. 3149502000019 DECAY-DATA (38-SR-87-M,2.795HR,DG,388.40,.823) 3149502000020 STATUS (TABLE) Data are taken from table 4 of Nuclear Science 3149502000021 and Engineering, vol. 129, pp. 164-174 (1998). 3149502000022 HISTORY (20150508U) VS. REL-REF added. INC-SPECT inf. added. 3149502000023 ENDBIB 21 0 3149502000024 COMMON 1 3 3149502000025 EN-MEAN 3149502000026 MEV 3149502000027 4.3 3149502000028 ENDCOMMON 3 0 3149502000029 DATA 2 1 3149502000030 DATA ERR-T 3149502000031 MB MB 3149502000032 .12 .02 3149502000033 ENDDATA 3 0 3149502000034 ENDSUBENT 33 0 3149502099999 SUBENT 31495021 20150508 31703149502100001 BIB 8 23 3149502100002 REACTION (40-ZR-94(N,A)38-SR-91,,SIG,,SPA) 3149502100003 INC-SOURCE (D-BE) Neutrons were produced by bombarding a 3 mm 3149502100004 thick Be target with 9.72 MeV deuterons. 3149502100005 INC-SPECT The volume-averaged flux density spectra of the neu- 3149502100006 trons was determined via the multiple foil activation 3149502100007 technique and spectrum unfolding. The average energy 3149502100008 is 4.3 MeV ( J.Csikai, private communication) 3149502100009 Incident neutron flux energy distribution in 3149502100010 Subentry D0055002. 3149502100011 REL-REF (N,D0055002,L.Olah+,J,NIM/A,404,373,1998) Incident 3149502100012 neutron flux energy distribution. 3149502100013 METHOD (STTA) Stacks of high-purity Fe,V,Co,Zn,Zr,Nb,Mo,Ni,Al,3149502100014 Sc and Ti foils with a set of Al,In,Fe,Ti,Au,Nb,Ni and 3149502100015 Zr foils as threshold detectors. Alluminium foils 3149502100016 placed at different positions within the stack were 3149502100017 applied to estimate the neutron flux attenuation in 3149502100018 the stack. 3149502100019 DECAY-DATA (38-SR-91,9.52HR,DG,555.56,.615, 3149502100020 DG,749.72,.236, 3149502100021 DG,1024.28,.33) 3149502100022 STATUS (TABLE) Data are taken from table 4 of Nuclear Science 3149502100023 and Engineering, vol. 129, pp. 164-174 (1998). 3149502100024 HISTORY (20150508U) VS. REL-REF added. INC-SPECT inf. added. 3149502100025 ENDBIB 23 0 3149502100026 COMMON 1 3 3149502100027 EN-MEAN 3149502100028 MEV 3149502100029 4.3 3149502100030 ENDCOMMON 3 0 3149502100031 DATA 2 1 3149502100032 DATA ERR-T 3149502100033 MB MB 3149502100034 .17 .02 3149502100035 ENDDATA 3 0 3149502100036 ENDSUBENT 35 0 3149502199999 SUBENT 31495022 20150508 31703149502200001 BIB 8 22 3149502200002 REACTION (41-NB-93(N,A)39-Y-90-M,,SIG,,SPA) 3149502200003 INC-SOURCE (D-BE) Neutrons were produced by bombarding a 3 mm 3149502200004 thick Be target with 9.72 MeV deuterons. 3149502200005 INC-SPECT The volume-averaged flux density spectra of the neu- 3149502200006 trons was determined via the multiple foil activation 3149502200007 technique and spectrum unfolding. The average energy 3149502200008 is 4.3 MeV ( J.Csikai, private communication) 3149502200009 Incident neutron flux energy distribution in 3149502200010 Subentry D0055002. 3149502200011 REL-REF (N,D0055002,L.Olah+,J,NIM/A,404,373,1998) Incident 3149502200012 neutron flux energy distribution. 3149502200013 METHOD (STTA) Stacks of high-purity Fe,V,Co,Zn,Zr,Nb,Mo,Ni,Al,3149502200014 Sc and Ti foils with a set of Al,In,Fe,Ti,Au,Nb,Ni and 3149502200015 Zr foils as threshold detectors. Alluminium foils 3149502200016 placed at different positions within the stack were 3149502200017 applied to estimate the neutron flux attenuation in 3149502200018 the stack. 3149502200019 DECAY-DATA (39-Y-90-M,3.19HR,DG,202.47,.966, 3149502200020 DG,479.49,.91) 3149502200021 STATUS (TABLE) Data are taken from table 4 of Nuclear Science 3149502200022 and Engineering, vol. 129, pp. 164-174 (1998). 3149502200023 HISTORY (20150508U) VS. REL-REF added. INC-SPECT inf. added. 3149502200024 ENDBIB 22 0 3149502200025 COMMON 1 3 3149502200026 EN-MEAN 3149502200027 MEV 3149502200028 4.3 3149502200029 ENDCOMMON 3 0 3149502200030 DATA 2 1 3149502200031 DATA ERR-T 3149502200032 MB MB 3149502200033 .23 .03 3149502200034 ENDDATA 3 0 3149502200035 ENDSUBENT 34 0 3149502299999 SUBENT 31495023 20150508 31703149502300001 BIB 8 21 3149502300002 REACTION (42-MO-92(N,A)40-ZR-89,,SIG,,SPA) 3149502300003 INC-SOURCE (D-BE) Neutrons were produced by bombarding a 3 mm 3149502300004 thick Be target with 9.72 MeV deuterons. 3149502300005 INC-SPECT The volume-averaged flux density spectra of the neu- 3149502300006 trons was determined via the multiple foil activation 3149502300007 technique and spectrum unfolding. The average energy 3149502300008 is 4.3 MeV ( J.Csikai, private communication) 3149502300009 Incident neutron flux energy distribution in 3149502300010 Subentry D0055002. 3149502300011 REL-REF (N,D0055002,L.Olah+,J,NIM/A,404,373,1998) Incident 3149502300012 neutron flux energy distribution. 3149502300013 METHOD (STTA) Stacks of high-purity Fe,V,Co,Zn,Zr,Nb,Mo,Ni,Al,3149502300014 Sc and Ti foils with a set of Al,In,Fe,Ti,Au,Nb,Ni and 3149502300015 Zr foils as threshold detectors. Alluminium foils 3149502300016 placed at different positions within the stack were 3149502300017 applied to estimate the neutron flux attenuation in 3149502300018 the stack. 3149502300019 DECAY-DATA (40-ZR-89-G,3.268D,DG,909.15,.9901) 3149502300020 STATUS (TABLE) Data are taken from table 4 of Nuclear Science 3149502300021 and Engineering, vol. 129, pp. 164-174 (1998). 3149502300022 HISTORY (20150508U) VS. REL-REF added. INC-SPECT inf. added. 3149502300023 ENDBIB 21 0 3149502300024 COMMON 1 3 3149502300025 EN-MEAN 3149502300026 MEV 3149502300027 4.3 3149502300028 ENDCOMMON 3 0 3149502300029 DATA 2 1 3149502300030 DATA ERR-T 3149502300031 MB MB 3149502300032 .93 .10 3149502300033 ENDDATA 3 0 3149502300034 ENDSUBENT 33 0 3149502399999 SUBENT 31495024 20150508 31703149502400001 BIB 7 20 3149502400002 REACTION (28-NI-62(N,A)26-FE-59,,SIG,,SPA) 3149502400003 INC-SOURCE (D-BE) Neutrons were produced by bombarding a 3 mm 3149502400004 thick Be target with 9.72 MeV deuterons. 3149502400005 INC-SPECT The volume-averaged flux density spectra of the neu- 3149502400006 trons was determined via the multiple foil activation 3149502400007 technique and spectrum unfolding. The average energy 3149502400008 is 4.3 MeV ( J.Csikai, private communication) 3149502400009 Incident neutron flux energy distribution in 3149502400010 Subentry D0055002. 3149502400011 REL-REF (N,D0055002,L.Olah+,J,NIM/A,404,373,1998) Incident 3149502400012 neutron flux energy distribution. 3149502400013 METHOD (STTA) Stacks of high-purity Fe,V,Co,Zn,Zr,Nb,Mo,Ni,Al,3149502400014 Sc and Ti foils with a set of Al,In,Fe,Ti,Au,Nb,Ni and 3149502400015 Zr foils as threshold detectors. Alluminium foils 3149502400016 placed at different positions within the stack were 3149502400017 applied to estimate the neutron flux attenuation in 3149502400018 the stack. 3149502400019 STATUS (TABLE) Data are taken from table 4 of Nuclear Science 3149502400020 and Engineering, vol. 129, pp. 164-174 (1998). 3149502400021 HISTORY (20150508U) VS. REL-REF added. INC-SPECT inf. added. 3149502400022 ENDBIB 20 0 3149502400023 COMMON 1 3 3149502400024 EN-MEAN 3149502400025 MEV 3149502400026 4.3 3149502400027 ENDCOMMON 3 0 3149502400028 DATA 2 1 3149502400029 DATA ERR-T 3149502400030 MB MB 3149502400031 .81 .09 3149502400032 ENDDATA 3 0 3149502400033 ENDSUBENT 32 0 3149502499999 SUBENT 31495025 20150508 31703149502500001 BIB 8 21 3149502500002 REACTION (13-AL-27(N,A)11-NA-24,,SIG,,SPA) 3149502500003 INC-SOURCE (D-BE) Neutrons were produced by bombarding a 3 mm 3149502500004 thick Be target with 9.72 MeV deuterons. 3149502500005 INC-SPECT The volume-averaged flux density spectra of the neu- 3149502500006 trons was determined via the multiple foil activation 3149502500007 technique and spectrum unfolding. The average energy 3149502500008 is 4.3 MeV ( J.Csikai, private communication) 3149502500009 Incident neutron flux energy distribution in 3149502500010 Subentry D0055002. 3149502500011 REL-REF (N,D0055002,L.Olah+,J,NIM/A,404,373,1998) Incident 3149502500012 neutron flux energy distribution. 3149502500013 METHOD (STTA) Stacks of high-purity Fe,V,Co,Zn,Zr,Nb,Mo,Ni,Al,3149502500014 Sc and Ti foils with a set of Al,In,Fe,Ti,Au,Nb,Ni and 3149502500015 Zr foils as threshold detectors. Alluminium foils 3149502500016 placed at different positions within the stack were 3149502500017 applied to estimate the neutron flux attenuation in 3149502500018 the stack. 3149502500019 DECAY-DATA (11-NA-24,14.659HR,DG,1368.598,1.) 3149502500020 STATUS (TABLE) Data are taken from table 4 of Nuclear Science 3149502500021 and Engineering, vol. 129, pp. 164-174 (1998). 3149502500022 HISTORY (20150508U) VS. REL-REF added. INC-SPECT inf. added. 3149502500023 ENDBIB 21 0 3149502500024 COMMON 1 3 3149502500025 EN-MEAN 3149502500026 MEV 3149502500027 4.3 3149502500028 ENDCOMMON 3 0 3149502500029 DATA 2 1 3149502500030 DATA ERR-T 3149502500031 MB MB 3149502500032 12.2 1.3 3149502500033 ENDDATA 3 0 3149502500034 ENDSUBENT 33 0 3149502599999 SUBENT 31495026 20150508 31703149502600001 BIB 8 21 3149502600002 REACTION (21-SC-45(N,A)19-K-42,,SIG,,SPA) 3149502600003 INC-SOURCE (D-BE) Neutrons were produced by bombarding a 3 mm 3149502600004 thick Be target with 9.72 MeV deuterons. 3149502600005 INC-SPECT The volume-averaged flux density spectra of the neu- 3149502600006 trons was determined via the multiple foil activation 3149502600007 technique and spectrum unfolding. The average energy 3149502600008 is 4.3 MeV ( J.Csikai, private communication) 3149502600009 Incident neutron flux energy distribution in 3149502600010 Subentry D0055002. 3149502600011 REL-REF (N,D0055002,L.Olah+,J,NIM/A,404,373,1998) Incident 3149502600012 neutron flux energy distribution. 3149502600013 METHOD (STTA) Stacks of high-purity Fe,V,Co,Zn,Zr,Nb,Mo,Ni,Al,3149502600014 Sc and Ti foils with a set of Al,In,Fe,Ti,Au,Nb,Ni and 3149502600015 Zr foils as threshold detectors. Alluminium foils 3149502600016 placed at different positions within the stack were 3149502600017 applied to estimate the neutron flux attenuation in 3149502600018 the stack. 3149502600019 DECAY-DATA (19-K-42,12.360HR,DG,1524.58,.188) 3149502600020 STATUS (TABLE) Data are taken from table 4 of Nuclear Science 3149502600021 and Engineering, vol. 129, pp. 164-174 (1998). 3149502600022 HISTORY (20150508U) VS. REL-REF added. INC-SPECT inf. added. 3149502600023 ENDBIB 21 0 3149502600024 COMMON 1 3 3149502600025 EN-MEAN 3149502600026 MEV 3149502600027 4.3 3149502600028 ENDCOMMON 3 0 3149502600029 DATA 2 1 3149502600030 DATA ERR-T 3149502600031 MB MB 3149502600032 3.05 .40 3149502600033 ENDDATA 3 0 3149502600034 ENDSUBENT 33 0 3149502699999 SUBENT 31495027 20150508 31703149502700001 BIB 8 21 3149502700002 REACTION (28-NI-58(N,P)27-CO-58,,SIG,,SPA) 3149502700003 INC-SOURCE (D-BE) Neutrons were produced by bombarding a 3 mm 3149502700004 thick Be target with 9.72 MeV deuterons. 3149502700005 INC-SPECT The volume-averaged flux density spectra of the neu- 3149502700006 trons was determined via the multiple foil activation 3149502700007 technique and spectrum unfolding. The average energy 3149502700008 is 4.3 MeV ( J.Csikai, private communication) 3149502700009 Incident neutron flux energy distribution in 3149502700010 Subentry D0055002. 3149502700011 REL-REF (N,D0055002,L.Olah+,J,NIM/A,404,373,1998) Incident 3149502700012 neutron flux energy distribution. 3149502700013 METHOD (STTA) Stacks of high-purity Fe,V,Co,Zn,Zr,Nb,Mo,Ni,Al,3149502700014 Sc and Ti foils with a set of Al,In,Fe,Ti,Au,Nb,Ni and 3149502700015 Zr foils as threshold detectors. Alluminium foils 3149502700016 placed at different positions within the stack were 3149502700017 applied to estimate the neutron flux attenuation in 3149502700018 the stack. 3149502700019 DECAY-DATA (27-CO-58-G,70.916D,DG,810.791,.995) 3149502700020 STATUS (TABLE) Data are taken from table 5 of Nuclear Science 3149502700021 and Engineering, vol. 129, pp. 164-174 (1998). 3149502700022 HISTORY (20150508U) VS. REL-REF added. INC-SPECT inf. added. 3149502700023 ENDBIB 21 0 3149502700024 COMMON 1 3 3149502700025 EN-MEAN 3149502700026 MEV 3149502700027 4.3 3149502700028 ENDCOMMON 3 0 3149502700029 DATA 2 1 3149502700030 DATA ERR-T 3149502700031 MB MB 3149502700032 325.65 30. 3149502700033 ENDDATA 3 0 3149502700034 ENDSUBENT 33 0 3149502799999 SUBENT 31495028 20150508 31703149502800001 BIB 8 22 3149502800002 REACTION (28-NI-60(N,P)27-CO-60,,SIG,,SPA) 3149502800003 INC-SOURCE (D-BE) Neutrons were produced by bombarding a 3 mm 3149502800004 thick Be target with 9.72 MeV deuterons. 3149502800005 INC-SPECT The volume-averaged flux density spectra of the neu- 3149502800006 trons was determined via the multiple foil activation 3149502800007 technique and spectrum unfolding. The average energy 3149502800008 is 4.3 MeV ( J.Csikai, private communication) 3149502800009 Incident neutron flux energy distribution in 3149502800010 Subentry D0055002. 3149502800011 REL-REF (N,D0055002,L.Olah+,J,NIM/A,404,373,1998) Incident 3149502800012 neutron flux energy distribution. 3149502800013 METHOD (STTA) Stacks of high-purity Fe,V,Co,Zn,Zr,Nb,Mo,Ni,Al,3149502800014 Sc and Ti foils with a set of Al,In,Fe,Ti,Au,Nb,Ni and 3149502800015 Zr foils as threshold detectors. Alluminium foils 3149502800016 placed at different positions within the stack were 3149502800017 applied to estimate the neutron flux attenuation in 3149502800018 the stack. 3149502800019 DECAY-DATA (27-CO-60-G,5.271YR,DG,1173.231,.999, 3149502800020 DG,1332.501,.999824) 3149502800021 STATUS (TABLE) Data are taken from table 5 of Nuclear Science 3149502800022 and Engineering, vol. 129, pp. 164-174 (1998). 3149502800023 HISTORY (20150508U) VS. REL-REF added. INC-SPECT inf. added. 3149502800024 ENDBIB 22 0 3149502800025 COMMON 1 3 3149502800026 EN-MEAN 3149502800027 MEV 3149502800028 4.3 3149502800029 ENDCOMMON 3 0 3149502800030 DATA 2 1 3149502800031 DATA ERR-T 3149502800032 MB MB 3149502800033 18.54 1.9 3149502800034 ENDDATA 3 0 3149502800035 ENDSUBENT 34 0 3149502899999 SUBENT 31495029 20150508 31703149502900001 BIB 8 21 3149502900002 REACTION (30-ZN-64(N,P)29-CU-64,,SIG,,SPA) 3149502900003 INC-SOURCE (D-BE) Neutrons were produced by bombarding a 3 mm 3149502900004 thick Be target with 9.72 MeV deuterons. 3149502900005 INC-SPECT The volume-averaged flux density spectra of the neu- 3149502900006 trons was determined via the multiple foil activation 3149502900007 technique and spectrum unfolding. The average energy 3149502900008 is 4.3 MeV ( J.Csikai, private communication) 3149502900009 Incident neutron flux energy distribution in 3149502900010 Subentry D0055002. 3149502900011 REL-REF (N,D0055002,L.Olah+,J,NIM/A,404,373,1998) Incident 3149502900012 neutron flux energy distribution. 3149502900013 METHOD (STTA) Stacks of high-purity Fe,V,Co,Zn,Zr,Nb,Mo,Ni,Al,3149502900014 Sc and Ti foils with a set of Al,In,Fe,Ti,Au,Nb,Ni and 3149502900015 Zr foils as threshold detectors. Alluminium foils 3149502900016 placed at different positions within the stack were 3149502900017 applied to estimate the neutron flux attenuation in 3149502900018 the stack. 3149502900019 DECAY-DATA (29-CU-64,12.701HR,DG,1345.78,.0048) 3149502900020 STATUS (TABLE) Data are taken from table 5 of Nuclear Science 3149502900021 and Engineering, vol. 129, pp. 164-174 (1998). 3149502900022 HISTORY (20150508U) VS. REL-REF added. INC-SPECT inf. added. 3149502900023 ENDBIB 21 0 3149502900024 COMMON 1 3 3149502900025 EN-MEAN 3149502900026 MEV 3149502900027 4.3 3149502900028 ENDCOMMON 3 0 3149502900029 DATA 2 1 3149502900030 DATA ERR-T 3149502900031 MB MB 3149502900032 111.34 10. 3149502900033 ENDDATA 3 0 3149502900034 ENDSUBENT 33 0 3149502999999 SUBENT 31495030 20150508 31703149503000001 BIB 8 22 3149503000002 REACTION (27-CO-59(N,P)26-FE-59,,SIG,,SPA) 3149503000003 INC-SOURCE (D-BE) Neutrons were produced by bombarding a 3 mm 3149503000004 thick Be target with 9.72 MeV deuterons. 3149503000005 INC-SPECT The volume-averaged flux density spectra of the neu- 3149503000006 trons was determined via the multiple foil activation 3149503000007 technique and spectrum unfolding. The average energy 3149503000008 is 4.3 MeV ( J.Csikai, private communication) 3149503000009 Incident neutron flux energy distribution in 3149503000010 Subentry D0055002. 3149503000011 REL-REF (N,D0055002,L.Olah+,J,NIM/A,404,373,1998) Incident 3149503000012 neutron flux energy distribution. 3149503000013 METHOD (STTA) Stacks of high-purity Fe,V,Co,Zn,Zr,Nb,Mo,Ni,Al,3149503000014 Sc and Ti foils with a set of Al,In,Fe,Ti,Au,Nb,Ni and 3149503000015 Zr foils as threshold detectors. Alluminium foils 3149503000016 placed at different positions within the stack were 3149503000017 applied to estimate the neutron flux attenuation in 3149503000018 the stack. 3149503000019 DECAY-DATA (26-FE-59,44.496D,DG,1099.251,.565, 3149503000020 DG,1291.596,.432) 3149503000021 STATUS (TABLE) Data are taken from table 5 of Nuclear Science 3149503000022 and Engineering, vol. 129, pp. 164-174 (1998). 3149503000023 HISTORY (20150508U) VS. REL-REF added. INC-SPECT inf. added. 3149503000024 ENDBIB 22 0 3149503000025 COMMON 1 3 3149503000026 EN-MEAN 3149503000027 MEV 3149503000028 4.3 3149503000029 ENDCOMMON 3 0 3149503000030 DATA 2 1 3149503000031 DATA ERR-T 3149503000032 MB MB 3149503000033 9.01 .9 3149503000034 ENDDATA 3 0 3149503000035 ENDSUBENT 34 0 3149503099999 SUBENT 31495031 20150508 31703149503100001 BIB 8 22 3149503100002 REACTION (40-ZR-90(N,P)39-Y-90-M,,SIG,,SPA) 3149503100003 INC-SOURCE (D-BE) Neutrons were produced by bombarding a 3 mm 3149503100004 thick Be target with 9.72 MeV deuterons. 3149503100005 INC-SPECT The volume-averaged flux density spectra of the neu- 3149503100006 trons was determined via the multiple foil activation 3149503100007 technique and spectrum unfolding. The average energy 3149503100008 is 4.3 MeV ( J.Csikai, private communication) 3149503100009 Incident neutron flux energy distribution in 3149503100010 Subentry D0055002. 3149503100011 REL-REF (N,D0055002,L.Olah+,J,NIM/A,404,373,1998) Incident 3149503100012 neutron flux energy distribution. 3149503100013 METHOD (STTA) Stacks of high-purity Fe,V,Co,Zn,Zr,Nb,Mo,Ni,Al,3149503100014 Sc and Ti foils with a set of Al,In,Fe,Ti,Au,Nb,Ni and 3149503100015 Zr foils as threshold detectors. Alluminium foils 3149503100016 placed at different positions within the stack were 3149503100017 applied to estimate the neutron flux attenuation in 3149503100018 the stack. 3149503100019 DECAY-DATA (39-Y-90-M,3.19HR,DG,202.47,.966, 3149503100020 DG,479.49,.91) 3149503100021 STATUS (TABLE) Data are taken from table 5 of Nuclear Science 3149503100022 and Engineering, vol. 129, pp. 164-174 (1998). 3149503100023 HISTORY (20150508U) VS. REL-REF added. INC-SPECT inf. added. 3149503100024 ENDBIB 22 0 3149503100025 COMMON 1 3 3149503100026 EN-MEAN 3149503100027 MEV 3149503100028 4.3 3149503100029 ENDCOMMON 3 0 3149503100030 DATA 2 1 3149503100031 DATA ERR-T 3149503100032 MB MB 3149503100033 0.56 .05 3149503100034 ENDDATA 3 0 3149503100035 ENDSUBENT 34 0 3149503199999 SUBENT 31495032 20150508 31703149503200001 BIB 8 21 3149503200002 REACTION (40-ZR-91(N,P)39-Y-91-M,,SIG,,SPA) 3149503200003 INC-SOURCE (D-BE) Neutrons were produced by bombarding a 3 mm 3149503200004 thick Be target with 9.72 MeV deuterons. 3149503200005 INC-SPECT The volume-averaged flux density spectra of the neu- 3149503200006 trons was determined via the multiple foil activation 3149503200007 technique and spectrum unfolding. The average energy 3149503200008 is 4.3 MeV ( J.Csikai, private communication) 3149503200009 Incident neutron flux energy distribution in 3149503200010 Subentry D0055002. 3149503200011 REL-REF (N,D0055002,L.Olah+,J,NIM/A,404,373,1998) Incident 3149503200012 neutron flux energy distribution. 3149503200013 METHOD (STTA) Stacks of high-purity Fe,V,Co,Zn,Zr,Nb,Mo,Ni,Al,3149503200014 Sc and Ti foils with a set of Al,In,Fe,Ti,Au,Nb,Ni and 3149503200015 Zr foils as threshold detectors. Alluminium foils 3149503200016 placed at different positions within the stack were 3149503200017 applied to estimate the neutron flux attenuation in 3149503200018 the stack. 3149503200019 DECAY-DATA (39-Y-91-M,49.71MIN,DG,555.56,.9490) 3149503200020 STATUS (TABLE) Data are taken from table 5 of Nuclear Science 3149503200021 and Engineering, vol. 129, pp. 164-174 (1998). 3149503200022 HISTORY (20150508U) VS. REL-REF added. INC-SPECT inf. added. 3149503200023 ENDBIB 21 0 3149503200024 COMMON 1 3 3149503200025 EN-MEAN 3149503200026 MEV 3149503200027 4.3 3149503200028 ENDCOMMON 3 0 3149503200029 DATA 2 1 3149503200030 DATA ERR-T 3149503200031 MB MB 3149503200032 0.86 0.09 3149503200033 ENDDATA 3 0 3149503200034 ENDSUBENT 33 0 3149503299999 SUBENT 31495033 20150508 31703149503300001 BIB 8 21 3149503300002 REACTION (40-ZR-92(N,P)39-Y-92,,SIG,,SPA) 3149503300003 INC-SOURCE (D-BE) Neutrons were produced by bombarding a 3 mm 3149503300004 thick Be target with 9.72 MeV deuterons. 3149503300005 INC-SPECT The volume-averaged flux density spectra of the neu- 3149503300006 trons was determined via the multiple foil activation 3149503300007 technique and spectrum unfolding. The average energy 3149503300008 is 4.3 MeV ( J.Csikai, private communication) 3149503300009 Incident neutron flux energy distribution in 3149503300010 Subentry D0055002. 3149503300011 REL-REF (N,D0055002,L.Olah+,J,NIM/A,404,373,1998) Incident 3149503300012 neutron flux energy distribution. 3149503300013 METHOD (STTA) Stacks of high-purity Fe,V,Co,Zn,Zr,Nb,Mo,Ni,Al,3149503300014 Sc and Ti foils with a set of Al,In,Fe,Ti,Au,Nb,Ni and 3149503300015 Zr foils as threshold detectors. Alluminium foils 3149503300016 placed at different positions within the stack were 3149503300017 applied to estimate the neutron flux attenuation in 3149503300018 the stack. 3149503300019 DECAY-DATA (39-Y-92,3.54HR,DG,934.53,.139) 3149503300020 STATUS (TABLE) Data are taken from table 5 of Nuclear Science 3149503300021 and Engineering, vol. 129, pp. 164-174 (1998). 3149503300022 HISTORY (20150508U) VS. REL-REF added. INC-SPECT inf. added. 3149503300023 ENDBIB 21 0 3149503300024 COMMON 1 3 3149503300025 EN-MEAN 3149503300026 MEV 3149503300027 4.3 3149503300028 ENDCOMMON 3 0 3149503300029 DATA 2 1 3149503300030 DATA ERR-T 3149503300031 MB MB 3149503300032 0.59 0.06 3149503300033 ENDDATA 3 0 3149503300034 ENDSUBENT 33 0 3149503399999 SUBENT 31495034 20150508 31703149503400001 BIB 8 21 3149503400002 REACTION (40-ZR-94(N,P)39-Y-94,,SIG,,SPA) 3149503400003 INC-SOURCE (D-BE) Neutrons were produced by bombarding a 3 mm 3149503400004 thick Be target with 9.72 MeV deuterons. 3149503400005 INC-SPECT The volume-averaged flux density spectra of the neu- 3149503400006 trons was determined via the multiple foil activation 3149503400007 technique and spectrum unfolding. The average energy 3149503400008 is 4.3 MeV ( J.Csikai, private communication) 3149503400009 Incident neutron flux energy distribution in 3149503400010 Subentry D0055002. 3149503400011 REL-REF (N,D0055002,L.Olah+,J,NIM/A,404,373,1998) Incident 3149503400012 neutron flux energy distribution. 3149503400013 METHOD (STTA) Stacks of high-purity Fe,V,Co,Zn,Zr,Nb,Mo,Ni,Al,3149503400014 Sc and Ti foils with a set of Al,In,Fe,Ti,Au,Nb,Ni and 3149503400015 Zr foils as threshold detectors. Alluminium foils 3149503400016 placed at different positions within the stack were 3149503400017 applied to estimate the neutron flux attenuation in 3149503400018 the stack. 3149503400019 DECAY-DATA (39-Y-94,18.7MIN,DG,918.74,.56) 3149503400020 STATUS (TABLE) Data are taken from table 5 of Nuclear Science 3149503400021 and Engineering, vol. 129, pp. 164-174 (1998). 3149503400022 HISTORY (20150508U) VS. REL-REF added. INC-SPECT inf. added. 3149503400023 ENDBIB 21 0 3149503400024 COMMON 1 3 3149503400025 EN-MEAN 3149503400026 MEV 3149503400027 4.3 3149503400028 ENDCOMMON 3 0 3149503400029 DATA 2 1 3149503400030 DATA ERR-T 3149503400031 MB MB 3149503400032 0.12 0.02 3149503400033 ENDDATA 3 0 3149503400034 ENDSUBENT 33 0 3149503499999 SUBENT 31495035 20150508 31703149503500001 BIB 8 21 3149503500002 REACTION (42-MO-92(N,P)41-NB-92-M,,SIG,,SPA) 3149503500003 INC-SOURCE (D-BE) Neutrons were produced by bombarding a 3 mm 3149503500004 thick Be target with 9.72 MeV deuterons. 3149503500005 INC-SPECT The volume-averaged flux density spectra of the neu- 3149503500006 trons was determined via the multiple foil activation 3149503500007 technique and spectrum unfolding. The average energy 3149503500008 is 4.3 MeV ( J.Csikai, private communication) 3149503500009 Incident neutron flux energy distribution in 3149503500010 Subentry D0055002. 3149503500011 REL-REF (N,D0055002,L.Olah+,J,NIM/A,404,373,1998) Incident 3149503500012 neutron flux energy distribution. 3149503500013 METHOD (STTA) Stacks of high-purity Fe,V,Co,Zn,Zr,Nb,Mo,Ni,Al,3149503500014 Sc and Ti foils with a set of Al,In,Fe,Ti,Au,Nb,Ni and 3149503500015 Zr foils as threshold detectors. Alluminium foils 3149503500016 placed at different positions within the stack were 3149503500017 applied to estimate the neutron flux attenuation in 3149503500018 the stack. 3149503500019 DECAY-DATA (41-NB-92-M,10.15D,DG,934.53,.99) 3149503500020 STATUS (TABLE) Data are taken from table 5 of Nuclear Science 3149503500021 and Engineering, vol. 129, pp. 164-174 (1998). 3149503500022 HISTORY (20150508U) VS. REL-REF added. INC-SPECT inf. added. 3149503500023 ENDBIB 21 0 3149503500024 COMMON 1 3 3149503500025 EN-MEAN 3149503500026 MEV 3149503500027 4.3 3149503500028 ENDCOMMON 3 0 3149503500029 DATA 2 1 3149503500030 DATA ERR-T 3149503500031 MB MB 3149503500032 34.42 4.0 3149503500033 ENDDATA 3 0 3149503500034 ENDSUBENT 33 0 3149503599999 SUBENT 31495036 20150508 31703149503600001 BIB 8 24 3149503600002 REACTION (42-MO-96(N,P)41-NB-96,,SIG,,SPA) 3149503600003 INC-SOURCE (D-BE) Neutrons were produced by bombarding a 3 mm 3149503600004 thick Be target with 9.72 MeV deuterons. 3149503600005 INC-SPECT The volume-averaged flux density spectra of the neu- 3149503600006 trons was determined via the multiple foil activation 3149503600007 technique and spectrum unfolding. The average energy 3149503600008 is 4.3 MeV ( J.Csikai, private communication) 3149503600009 Incident neutron flux energy distribution in 3149503600010 Subentry D0055002. 3149503600011 REL-REF (N,D0055002,L.Olah+,J,NIM/A,404,373,1998) Incident 3149503600012 neutron flux energy distribution. 3149503600013 METHOD (STTA) Stacks of high-purity Fe,V,Co,Zn,Zr,Nb,Mo,Ni,Al,3149503600014 Sc and Ti foils with a set of Al,In,Fe,Ti,Au,Nb,Ni and 3149503600015 Zr foils as threshold detectors. Alluminium foils 3149503600016 placed at different positions within the stack were 3149503600017 applied to estimate the neutron flux attenuation in 3149503600018 the stack. 3149503600019 DECAY-DATA (41-NB-96,23.35HR,DG,460.01,.285, 3149503600020 DG,568.86,.568, 3149503600021 DG,778.196,.9688, 3149503600022 DG,1091.316,.485) 3149503600023 STATUS (TABLE) Data are taken from table 5 of Nuclear Science 3149503600024 and Engineering, vol. 129, pp. 164-174 (1998). 3149503600025 HISTORY (20150508U) VS. REL-REF added. INC-SPECT inf. added. 3149503600026 ENDBIB 24 0 3149503600027 COMMON 1 3 3149503600028 EN-MEAN 3149503600029 MEV 3149503600030 4.3 3149503600031 ENDCOMMON 3 0 3149503600032 DATA 2 1 3149503600033 DATA ERR-T 3149503600034 MB MB 3149503600035 0.62 0.07 3149503600036 ENDDATA 3 0 3149503600037 ENDSUBENT 36 0 3149503699999 SUBENT 31495037 20150508 31703149503700001 BIB 8 21 3149503700002 REACTION (42-MO-97(N,P)41-NB-97,,SIG,,SPA) 3149503700003 INC-SOURCE (D-BE) Neutrons were produced by bombarding a 3 mm 3149503700004 thick Be target with 9.72 MeV deuterons. 3149503700005 INC-SPECT The volume-averaged flux density spectra of the neu- 3149503700006 trons was determined via the multiple foil activation 3149503700007 technique and spectrum unfolding. The average energy 3149503700008 is 4.3 MeV ( J.Csikai, private communication) 3149503700009 Incident neutron flux energy distribution in 3149503700010 Subentry D0055002. 3149503700011 REL-REF (N,D0055002,L.Olah+,J,NIM/A,404,373,1998) Incident 3149503700012 neutron flux energy distribution. 3149503700013 METHOD (STTA) Stacks of high-purity Fe,V,Co,Zn,Zr,Nb,Mo,Ni,Al,3149503700014 Sc and Ti foils with a set of Al,In,Fe,Ti,Au,Nb,Ni and 3149503700015 Zr foils as threshold detectors. Alluminium foils 3149503700016 placed at different positions within the stack were 3149503700017 applied to estimate the neutron flux attenuation in 3149503700018 the stack. 3149503700019 DECAY-DATA (41-NB-97-G,1.202HR,DG,658.22,.9834) 3149503700020 STATUS (TABLE) Data are taken from table 5 of Nuclear Science 3149503700021 and Engineering, vol. 129, pp. 164-174 (1998). 3149503700022 HISTORY (20150508U) VS. REL-REF added. INC-SPECT inf. added. 3149503700023 ENDBIB 21 0 3149503700024 COMMON 1 3 3149503700025 EN-MEAN 3149503700026 MEV 3149503700027 4.3 3149503700028 ENDCOMMON 3 0 3149503700029 DATA 2 1 3149503700030 DATA ERR-T 3149503700031 MB MB 3149503700032 0.43 0.05 3149503700033 ENDDATA 3 0 3149503700034 ENDSUBENT 33 0 3149503799999 SUBENT 31495038 20150508 31703149503800001 BIB 8 21 3149503800002 REACTION (26-FE-56(N,P)25-MN-56,,SIG,,SPA) 3149503800003 INC-SOURCE (D-BE) Neutrons were produced by bombarding a 3 mm 3149503800004 thick Be target with 9.72 MeV deuterons. 3149503800005 INC-SPECT The volume-averaged flux density spectra of the neu- 3149503800006 trons was determined via the multiple foil activation 3149503800007 technique and spectrum unfolding. The average energy 3149503800008 is 4.3 MeV ( J.Csikai, private communication) 3149503800009 Incident neutron flux energy distribution in 3149503800010 Subentry D0055002. 3149503800011 REL-REF (N,D0055002,L.Olah+,J,NIM/A,404,373,1998) Incident 3149503800012 neutron flux energy distribution. 3149503800013 METHOD (STTA) Stacks of high-purity Fe,V,Co,Zn,Zr,Nb,Mo,Ni,Al,3149503800014 Sc and Ti foils with a set of Al,In,Fe,Ti,Au,Nb,Ni and 3149503800015 Zr foils as threshold detectors. Alluminium foils 3149503800016 placed at different positions within the stack were 3149503800017 applied to estimate the neutron flux attenuation in 3149503800018 the stack. 3149503800019 DECAY-DATA (25-MN-56,2.5785HR,DG,846.812,.989) 3149503800020 STATUS (TABLE) Data are taken from table 5 of Nuclear Science 3149503800021 and Engineering, vol. 129, pp. 164-174 (1998). 3149503800022 HISTORY (20150508U) VS. REL-REF added. INC-SPECT inf. added. 3149503800023 ENDBIB 21 0 3149503800024 COMMON 1 3 3149503800025 EN-MEAN 3149503800026 MEV 3149503800027 4.3 3149503800028 ENDCOMMON 3 0 3149503800029 DATA 2 1 3149503800030 DATA ERR-T 3149503800031 MB MB 3149503800032 11.87 1.3 3149503800033 ENDDATA 3 0 3149503800034 ENDSUBENT 33 0 3149503899999 SUBENT 31495039 20150508 31703149503900001 BIB 8 22 3149503900002 REACTION (22-TI-46(N,P)21-SC-46,,SIG,,SPA) 3149503900003 INC-SOURCE (D-BE) Neutrons were produced by bombarding a 3 mm 3149503900004 thick Be target with 9.72 MeV deuterons. 3149503900005 INC-SPECT The volume-averaged flux density spectra of the neu- 3149503900006 trons was determined via the multiple foil activation 3149503900007 technique and spectrum unfolding. The average energy 3149503900008 is 4.3 MeV ( J.Csikai, private communication) 3149503900009 Incident neutron flux energy distribution in 3149503900010 Subentry D0055002. 3149503900011 REL-REF (N,D0055002,L.Olah+,J,NIM/A,404,373,1998) Incident 3149503900012 neutron flux energy distribution. 3149503900013 METHOD (STTA) Stacks of high-purity Fe,V,Co,Zn,Zr,Nb,Mo,Ni,Al,3149503900014 Sc and Ti foils with a set of Al,In,Fe,Ti,Au,Nb,Ni and 3149503900015 Zr foils as threshold detectors. Alluminium foils 3149503900016 placed at different positions within the stack were 3149503900017 applied to estimate the neutron flux attenuation in 3149503900018 the stack. 3149503900019 DECAY-DATA (21-SC-46-G,83.83D,DG,889.25,.99984, 3149503900020 DG,1120.51,.485) 3149503900021 STATUS (TABLE) Data are taken from table 5 of Nuclear Science 3149503900022 and Engineering, vol. 129, pp. 164-174 (1998). 3149503900023 HISTORY (20150508U) VS. REL-REF added. INC-SPECT inf. added. 3149503900024 ENDBIB 22 0 3149503900025 COMMON 1 3 3149503900026 EN-MEAN 3149503900027 MEV 3149503900028 4.3 3149503900029 ENDCOMMON 3 0 3149503900030 DATA 2 1 3149503900031 DATA ERR-T 3149503900032 MB MB 3149503900033 75.77 8.3 3149503900034 ENDDATA 3 0 3149503900035 ENDSUBENT 34 0 3149503999999 SUBENT 31495040 20150508 31703149504000001 BIB 8 21 3149504000002 REACTION (22-TI-47(N,P)21-SC-47,,SIG,,SPA) 3149504000003 INC-SOURCE (D-BE) Neutrons were produced by bombarding a 3 mm 3149504000004 thick Be target with 9.72 MeV deuterons. 3149504000005 INC-SPECT The volume-averaged flux density spectra of the neu- 3149504000006 trons was determined via the multiple foil activation 3149504000007 technique and spectrum unfolding. The average energy 3149504000008 is 4.3 MeV ( J.Csikai, private communication) 3149504000009 Incident neutron flux energy distribution in 3149504000010 Subentry D0055002. 3149504000011 REL-REF (N,D0055002,L.Olah+,J,NIM/A,404,373,1998) Incident 3149504000012 neutron flux energy distribution. 3149504000013 METHOD (STTA) Stacks of high-purity Fe,V,Co,Zn,Zr,Nb,Mo,Ni,Al,3149504000014 Sc and Ti foils with a set of Al,In,Fe,Ti,Au,Nb,Ni and 3149504000015 Zr foils as threshold detectors. Alluminium foils 3149504000016 placed at different positions within the stack were 3149504000017 applied to estimate the neutron flux attenuation in 3149504000018 the stack. 3149504000019 DECAY-DATA (21-SC-47,3.341D,DG,159.381,.68) 3149504000020 STATUS (TABLE) Data are taken from table 5 of Nuclear Science 3149504000021 and Engineering, vol. 129, pp. 164-174 (1998). 3149504000022 HISTORY (20150508U) VS. REL-REF added. INC-SPECT inf. added. 3149504000023 ENDBIB 21 0 3149504000024 COMMON 1 3 3149504000025 EN-MEAN 3149504000026 MEV 3149504000027 4.3 3149504000028 ENDCOMMON 3 0 3149504000029 DATA 2 1 3149504000030 DATA ERR-T 3149504000031 MB MB 3149504000032 51.39 5.7 3149504000033 ENDDATA 3 0 3149504000034 ENDSUBENT 33 0 3149504099999 SUBENT 31495041 20150508 31703149504100001 BIB 8 23 3149504100002 REACTION (22-TI-48(N,P)21-SC-48,,SIG,,SPA) 3149504100003 INC-SOURCE (D-BE) Neutrons were produced by bombarding a 3 mm 3149504100004 thick Be target with 9.72 MeV deuterons. 3149504100005 INC-SPECT The volume-averaged flux density spectra of the neu- 3149504100006 trons was determined via the multiple foil activation 3149504100007 technique and spectrum unfolding. The average energy 3149504100008 is 4.3 MeV ( J.Csikai, private communication) 3149504100009 Incident neutron flux energy distribution in 3149504100010 Subentry D0055002. 3149504100011 REL-REF (N,D0055002,L.Olah+,J,NIM/A,404,373,1998) Incident 3149504100012 neutron flux energy distribution. 3149504100013 METHOD (STTA) Stacks of high-purity Fe,V,Co,Zn,Zr,Nb,Mo,Ni,Al,3149504100014 Sc and Ti foils with a set of Al,In,Fe,Ti,Au,Nb,Ni and 3149504100015 Zr foils as threshold detectors. Alluminium foils 3149504100016 placed at different positions within the stack were 3149504100017 applied to estimate the neutron flux attenuation in 3149504100018 the stack. 3149504100019 DECAY-DATA (21-SC-48,1.821D,DG,983.501,1., 3149504100020 DG,1037.4961,.975, 3149504100021 DG,1312.046,1.) 3149504100022 STATUS (TABLE) Data are taken from table 5 of Nuclear Science 3149504100023 and Engineering, vol. 129, pp. 164-174 (1998). 3149504100024 HISTORY (20150508U) VS. REL-REF added. INC-SPECT inf. added. 3149504100025 ENDBIB 23 0 3149504100026 COMMON 1 3 3149504100027 EN-MEAN 3149504100028 MEV 3149504100029 4.3 3149504100030 ENDCOMMON 3 0 3149504100031 DATA 2 1 3149504100032 DATA ERR-T 3149504100033 MB MB 3149504100034 4.60 0.5 3149504100035 ENDDATA 3 0 3149504100036 ENDSUBENT 35 0 3149504199999 ENDENTRY 41 0 3149599999999