ENTRY 11850 20220822 15001185000000001 SUBENT 11850001 20220822 15001185000100001 BIB 10 15 1185000100002 INSTITUTE (1USAREN) 1185000100003 REFERENCE (J,ARI,18,279,1967) 1185000100004 AUTHOR (K.G.Broadhead,D.E.Shanks) 1185000100005 TITLE The application of 2.8 MeV (D,d) neutrons to activation1185000100006 analysis. 1185000100007 FACILITY (ACCEL,1USAREN) Model 9500 Texas Nuclear neutron 1185000100008 generator 1185000100009 INC-SOURCE (D-D) 1185000100010 METHOD (ACTIV) 1185000100011 MONITOR (49-IN-115(N,INL)49-IN-115-M,,SIG,G) 1185000100012 STATUS (TABLE) Table 1, J,ARI,18,279,1967 1185000100013 HISTORY (19760731T) Translated from SCISRS 1185000100014 (19830919A) Converted to reaction formalism 1185000100015 (20220814A) OS. REACTION corrected in Subs.10,11, 1185000100016 added ERR-ANALYS, STATUS, COMMENT in sub.4 1185000100017 ENDBIB 15 0 1185000100018 COMMON 1 3 1185000100019 MONIT 1185000100020 MB 1185000100021 360. 1185000100022 ENDCOMMON 3 0 1185000100023 ENDSUBENT 22 0 1185000199999 SUBENT 11850002 20220822 15001185000200001 BIB 3 17 1185000200002 REACTION (37-RB-85(N,G)37-RB-86-M,,SIG) 1185000200003 DECAY-DATA (37-RB-86-M,1.04MIN,DG,560.,1.0) 1185000200004 ERR-ANALYS (ERR-T) Quoted errors include the following sources 1185000200005 of uncertainties. Not included are uncertainties of 1185000200006 decay schemes and conversion coefficients. 1185000200007 (ERR-1) Neutron flux, 10% 1185000200008 (ERR-2,,6.) Gamma-ray attenuation by the samples 1185000200009 (ERR-3) Brief variations in flux, 2.5% 1185000200010 (ERR-4,,3.) Uncertainty in the reported half-lives 1185000200011 (ERR-5,,3.5) Non-reproducibility of irradiation and 1185000200012 delay times 1185000200013 (ERR-6) Counting efficiency 3.5% 1185000200014 (ERR-7) Fractional photopeak efficiency, 2.5% 1185000200015 (ERR-S,0.5,8.2) Statistical error in gamma counting, 1185000200016 on average 1.4% 1185000200017 (ERR-8,,0.5) Interference of (n,g) reactions by 1185000200018 thermal neutrons. 1185000200019 ENDBIB 17 0 1185000200020 COMMON 4 3 1185000200021 ERR-1 ERR-3 ERR-6 ERR-7 1185000200022 PER-CENT PER-CENT PER-CENT PER-CENT 1185000200023 10. 2.5 3.5 2.5 1185000200024 ENDCOMMON 3 0 1185000200025 DATA 4 1 1185000200026 EN EN-RSL DATA ERR-T 1185000200027 MEV MEV MB PER-CENT 1185000200028 2.80 +00 7. -02 4. +00 13. 1185000200029 ENDDATA 3 0 1185000200030 ENDSUBENT 29 0 1185000299999 SUBENT 11850003 20220822 15001185000300001 BIB 4 18 1185000300002 REACTION (39-Y-89(N,INL)39-Y-89-M,,SIG) 1185000300003 DECAY-DATA (39-Y-89-M,16.0SEC,DG,913.,1.0) 1185000300004 ERR-ANALYS (ERR-T) Quoted errors include the following sources 1185000300005 of uncertainties. Not included are uncertainties of 1185000300006 decay schemes and conversion coefficients. 1185000300007 (ERR-1) Neutron flux, 10% 1185000300008 (ERR-2,,6.) Gamma-ray attenuation by the samples 1185000300009 (ERR-3) Brief variations in flux, 2.5% 1185000300010 (ERR-4,,3.) Uncertainty in the reported half-lives 1185000300011 (ERR-5,,3.5) Non-reproducibility of irradiation and 1185000300012 delay times 1185000300013 (ERR-6) Counting efficiency 3.5% 1185000300014 (ERR-7) Fractional photopeak efficiency, 2.5% 1185000300015 (ERR-S,0.5,8.2) Statistical error in gamma counting, 1185000300016 on average 1.4% 1185000300017 (ERR-8,,0.5) Interference of (n,g) reactions by 1185000300018 thermal neutrons. 1185000300019 HISTORY (19860206A) Reaction corrected. 1185000300020 ENDBIB 18 0 1185000300021 COMMON 4 3 1185000300022 ERR-1 ERR-3 ERR-6 ERR-7 1185000300023 PER-CENT PER-CENT PER-CENT PER-CENT 1185000300024 10. 2.5 3.5 2.5 1185000300025 ENDCOMMON 3 0 1185000300026 DATA 4 1 1185000300027 EN EN-RSL DATA ERR-T 1185000300028 MEV MEV MB PER-CENT 1185000300029 2.80 +00 7. -02 2.51 +02 13. 1185000300030 ENDDATA 3 0 1185000300031 ENDSUBENT 30 0 1185000399999 SUBENT 11850004 20220822 15001185000400001 BIB 6 27 1185000400002 REACTION ((47-AG-107(N,INL)47-AG-107-M,,SIG)+ 1185000400003 (47-AG-109(N,INL)47-AG-109-M,,SIG)) 1185000400004 DECAY-DATA (47-AG-107-M,44.3SEC,DG/ICE,93.,1.0) 1185000400005 (47-AG-109-M,40.SEC,DG/ICE,88.,1.0) 1185000400006 COMMENT Comment by compiler: The value reported in Table I for 1185000400007 this sum of cross sections is not in agreement with 1185000400008 the value expected from other works in the literature 1185000400009 which should be around 1000 mb (compare e.g. T.Shimizu 1185000400010 et al., Ann.Nucl.En.31,1883,2004) 1185000400011 REL-REF (D,22838001,T.Shimizu+,J,ANE,31,1883,2004) 1185000400012 ERR-ANALYS (ERR-T) Quoted errors include the following sources 1185000400013 of uncertainties. Not included are uncertainties of 1185000400014 decay schemes and conversion coefficients. 1185000400015 (ERR-1) Neutron flux, 10% 1185000400016 (ERR-2,,6.) Gamma-ray attenuation by the samples 1185000400017 (ERR-3) Brief variations in flux, 2.5% 1185000400018 (ERR-4,,3.) Uncertainty in the reported half-lives 1185000400019 (ERR-5,,3.5) Non-reproducibility of irradiation and 1185000400020 delay times 1185000400021 (ERR-6) Counting efficiency 3.5% 1185000400022 (ERR-7) Fractional photopeak efficiency, 2.5% 1185000400023 (ERR-S,0.5,8.2) Statistical error in gamma counting, 1185000400024 on average 1.4% 1185000400025 (ERR-8,,0.5) Interference of (n,g) reactions by 1185000400026 thermal neutrons. 1185000400027 HISTORY (19860206A) Reaction corrected. 1185000400028 (20220814A) COMMENT and REL-REF added 1185000400029 ENDBIB 27 0 1185000400030 COMMON 4 3 1185000400031 ERR-1 ERR-3 ERR-6 ERR-7 1185000400032 PER-CENT PER-CENT PER-CENT PER-CENT 1185000400033 10. 2.5 3.5 2.5 1185000400034 ENDCOMMON 3 0 1185000400035 DATA 4 1 1185000400036 EN EN-RSL DATA ERR-T 1185000400037 MEV MEV MB PER-CENT 1185000400038 2.80 +00 7. -02 5.30 +02 13. 1185000400039 ENDDATA 3 0 1185000400040 ENDSUBENT 39 0 1185000499999 SUBENT 11850005 20220822 15001185000500001 BIB 4 18 1185000500002 REACTION (48-CD-111(N,INL)48-CD-111-M,,SIG) 1185000500003 DECAY-DATA (48-CD-111-M,48.7MIN,DG/ICE,246.,1.0) 1185000500004 ERR-ANALYS (ERR-T) Quoted errors include the following sources 1185000500005 of uncertainties. Not included are uncertainties of 1185000500006 decay schemes and conversion coefficients. 1185000500007 (ERR-1) Neutron flux, 10% 1185000500008 (ERR-2,,6.) Gamma-ray attenuation by the samples 1185000500009 (ERR-3) Brief variations in flux, 2.5% 1185000500010 (ERR-4,,3.) Uncertainty in the reported half-lives 1185000500011 (ERR-5,,3.5) Non-reproducibility of irradiation and 1185000500012 delay times 1185000500013 (ERR-6) Counting efficiency 3.5% 1185000500014 (ERR-7) Fractional photopeak efficiency, 2.5% 1185000500015 (ERR-S,0.5,8.2) Statistical error in gamma counting, 1185000500016 on average 1.4% 1185000500017 (ERR-8,,0.5) Interference of (n,g) reactions by 1185000500018 thermal neutrons. 1185000500019 HISTORY (19860206A) Reaction corrected. 1185000500020 ENDBIB 18 0 1185000500021 COMMON 4 3 1185000500022 ERR-1 ERR-3 ERR-6 ERR-7 1185000500023 PER-CENT PER-CENT PER-CENT PER-CENT 1185000500024 10. 2.5 3.5 2.5 1185000500025 ENDCOMMON 3 0 1185000500026 DATA 4 1 1185000500027 EN EN-RSL DATA ERR-T 1185000500028 MEV MEV MB PER-CENT 1185000500029 2.80 +00 7. -02 2.77 +02 13. 1185000500030 ENDDATA 3 0 1185000500031 ENDSUBENT 30 0 1185000599999 SUBENT 11850006 20220822 15001185000600001 BIB 4 18 1185000600002 REACTION (49-IN-115(N,G)49-IN-116-M1+M2,,SIG) 1185000600003 DECAY-DATA (49-IN-116-M1,53.99MIN,DG,1270.,0.83) 1185000600004 ERR-ANALYS (ERR-T) Quoted errors include the following sources 1185000600005 of uncertainties. Not included are uncertainties of 1185000600006 decay schemes and conversion coefficients. 1185000600007 (ERR-1) Neutron flux, 10% 1185000600008 (ERR-2,,6.) Gamma-ray attenuation by the samples 1185000600009 (ERR-3) Brief variations in flux, 2.5% 1185000600010 (ERR-4,,3.) Uncertainty in the reported half-lives 1185000600011 (ERR-5,,3.5) Non-reproducibility of irradiation and 1185000600012 delay times 1185000600013 (ERR-6) Counting efficiency 3.5% 1185000600014 (ERR-7) Fractional photopeak efficiency, 2.5% 1185000600015 (ERR-S,0.5,8.2) Statistical error in gamma counting, 1185000600016 on average 1.4% 1185000600017 (ERR-8,,0.5) Interference of (n,g) reactions by 1185000600018 thermal neutrons. 1185000600019 HISTORY (19860612A) Bib update. 1185000600020 ENDBIB 18 0 1185000600021 COMMON 4 3 1185000600022 ERR-1 ERR-3 ERR-6 ERR-7 1185000600023 PER-CENT PER-CENT PER-CENT PER-CENT 1185000600024 10. 2.5 3.5 2.5 1185000600025 ENDCOMMON 3 0 1185000600026 DATA 4 1 1185000600027 EN EN-RSL DATA ERR-T 1185000600028 MEV MEV MB PER-CENT 1185000600029 2.80 +00 7. -02 4.0 +01 13. 1185000600030 ENDDATA 3 0 1185000600031 ENDSUBENT 30 0 1185000699999 SUBENT 11850007 20220822 15001185000700001 BIB 4 18 1185000700002 REACTION (56-BA-137(N,INL)56-BA-137-M,,SIG) 1185000700003 DECAY-DATA (56-BA-137-M,2.6MIN,DG/ICE,661.,1.0) 1185000700004 ERR-ANALYS (ERR-T) Quoted errors include the following sources 1185000700005 of uncertainties. Not included are uncertainties of 1185000700006 decay schemes and conversion coefficients. 1185000700007 (ERR-1) Neutron flux, 10% 1185000700008 (ERR-2,,6.) Gamma-ray attenuation by the samples 1185000700009 (ERR-3) Brief variations in flux, 2.5% 1185000700010 (ERR-4,,3.) Uncertainty in the reported half-lives 1185000700011 (ERR-5,,3.5) Non-reproducibility of irradiation and 1185000700012 delay times 1185000700013 (ERR-6) Counting efficiency 3.5% 1185000700014 (ERR-7) Fractional photopeak efficiency, 2.5% 1185000700015 (ERR-S,0.5,8.2) Statistical error in gamma counting, 1185000700016 on average 1.4% 1185000700017 (ERR-8,,0.5) Interference of (n,g) reactions by 1185000700018 thermal neutrons. 1185000700019 HISTORY (19860206A) Reaction corrected. 1185000700020 ENDBIB 18 0 1185000700021 COMMON 4 3 1185000700022 ERR-1 ERR-3 ERR-6 ERR-7 1185000700023 PER-CENT PER-CENT PER-CENT PER-CENT 1185000700024 10. 2.5 3.5 2.5 1185000700025 ENDCOMMON 3 0 1185000700026 DATA 4 1 1185000700027 EN EN-RSL DATA ERR-T 1185000700028 MEV MEV B PER-CENT 1185000700029 2.80 +00 7. -02 4.65 -01 13. 1185000700030 ENDDATA 3 0 1185000700031 ENDSUBENT 30 0 1185000799999 SUBENT 11850008 20220822 15001185000800001 BIB 3 17 1185000800002 REACTION (64-GD-160(N,G)64-GD-161,,SIG) 1185000800003 DECAY-DATA (64-GD-161,3.7MIN,DG/ICE,360.,0.60) 1185000800004 ERR-ANALYS (ERR-T) Quoted errors include the following sources 1185000800005 of uncertainties. Not included are uncertainties of 1185000800006 decay schemes and conversion coefficients. 1185000800007 (ERR-1) Neutron flux, 10% 1185000800008 (ERR-2,,6.) Gamma-ray attenuation by the samples 1185000800009 (ERR-3) Brief variations in flux, 2.5% 1185000800010 (ERR-4,,3.) Uncertainty in the reported half-lives 1185000800011 (ERR-5,,3.5) Non-reproducibility of irradiation and 1185000800012 delay times 1185000800013 (ERR-6) Counting efficiency 3.5% 1185000800014 (ERR-7) Fractional photopeak efficiency, 2.5% 1185000800015 (ERR-S,0.5,8.2) Statistical error in gamma counting, 1185000800016 on average 1.4% 1185000800017 (ERR-8,,0.5) Interference of (n,g) reactions by 1185000800018 thermal neutrons. 1185000800019 ENDBIB 17 0 1185000800020 COMMON 4 3 1185000800021 ERR-1 ERR-3 ERR-6 ERR-7 1185000800022 PER-CENT PER-CENT PER-CENT PER-CENT 1185000800023 10. 2.5 3.5 2.5 1185000800024 ENDCOMMON 3 0 1185000800025 DATA 4 1 1185000800026 EN EN-RSL DATA ERR-T 1185000800027 MEV MEV B PER-CENT 1185000800028 2.80 +00 7. -02 1.7 -02 13. 1185000800029 ENDDATA 3 0 1185000800030 ENDSUBENT 29 0 1185000899999 SUBENT 11850009 20220822 15001185000900001 BIB 4 18 1185000900002 REACTION (68-ER-167(N,INL)68-ER-167-M,,SIG) 1185000900003 DECAY-DATA (68-ER-167-M,2.3SEC,DG/ICE,208.,1.0) 1185000900004 ERR-ANALYS (ERR-T) Quoted errors include the following sources 1185000900005 of uncertainties. Not included are uncertainties of 1185000900006 decay schemes and conversion coefficients. 1185000900007 (ERR-1) Neutron flux, 10% 1185000900008 (ERR-2,,6.) Gamma-ray attenuation by the samples 1185000900009 (ERR-3) Brief variations in flux, 2.5% 1185000900010 (ERR-4) Uncertainty in the reported half-live 1185000900011 (ERR-5,,3.5) Non-reproducibility of irradiation and 1185000900012 delay times 1185000900013 (ERR-6) Counting efficiency 3.5% 1185000900014 (ERR-7) Fractional photopeak efficiency, 2.5% 1185000900015 (ERR-S,0.5,8.2) Statistical error in gamma counting, 1185000900016 on average 1.4% 1185000900017 (ERR-8,,0.5) Interference of (n,g) reactions by 1185000900018 thermal neutrons. 1185000900019 HISTORY (19860206A) Reaction corrected. 1185000900020 ENDBIB 18 0 1185000900021 COMMON 5 3 1185000900022 ERR-1 ERR-3 ERR-4 ERR-6 ERR-7 1185000900023 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 1185000900024 10. 2.5 14. 3.5 2.5 1185000900025 ENDCOMMON 3 0 1185000900026 DATA 4 1 1185000900027 EN EN-RSL DATA ERR-T 1185000900028 MEV MEV B PER-CENT 1185000900029 2.80 +00 7. -02 7.90 -01 21. 1185000900030 ENDDATA 3 0 1185000900031 ENDSUBENT 30 0 1185000999999 SUBENT 11850010 20220822 15001185001000001 BIB 4 19 1185001000002 REACTION (72-HF-179(N,INL)72-HF-179-M1,,SIG) 1185001000003 DECAY-DATA (72-HF-179-M1,18.7SEC,DG/ICE,217.,1.0) 1185001000004 ERR-ANALYS (ERR-T) Quoted errors include the following sources 1185001000005 of uncertainties. Not included are uncertainties of 1185001000006 decay schemes and conversion coefficients. 1185001000007 (ERR-1) Neutron flux, 10% 1185001000008 (ERR-2,,6.) Gamma-ray attenuation by the samples 1185001000009 (ERR-3) Brief variations in flux, 2.5% 1185001000010 (ERR-4,,3.) Uncertainty in the reported half-lives 1185001000011 (ERR-5,,3.5) Non-reproducibility of irradiation and 1185001000012 delay times 1185001000013 (ERR-6) Counting efficiency 3.5% 1185001000014 (ERR-7) Fractional photopeak efficiency, 2.5% 1185001000015 (ERR-S,0.5,8.2) Statistical error in gamma counting, 1185001000016 on average 1.4% 1185001000017 (ERR-8,,18.) Interference of (n,g) reactions by 1185001000018 thermal neutrons. 1185001000019 HISTORY (19860206A) Reaction corrected. 1185001000020 (20220814A) REACTION SF4, DECAY-DATA: M -> M1 1185001000021 ENDBIB 19 0 1185001000022 COMMON 4 3 1185001000023 ERR-1 ERR-3 ERR-6 ERR-7 1185001000024 PER-CENT PER-CENT PER-CENT PER-CENT 1185001000025 10. 2.5 3.5 2.5 1185001000026 ENDCOMMON 3 0 1185001000027 DATA 4 1 1185001000028 EN EN-RSL DATA ERR-T 1185001000029 MEV MEV B PER-CENT 1185001000030 2.80 +00 7. -02 4.22 -01 21. 1185001000031 ENDDATA 3 0 1185001000032 ENDSUBENT 31 0 1185001099999 SUBENT 11850011 20220822 15001185001100001 BIB 4 19 1185001100002 REACTION (77-IR-191(N,INL)77-IR-191-M1,(M),SIG) 1185001100003 DECAY-DATA (77-IR-191-M1,4.9SEC,DG/ICE,129.,1.0) 1185001100004 ERR-ANALYS (ERR-T) Quoted errors include the following sources 1185001100005 of uncertainties. Not included are uncertainties of 1185001100006 decay schemes and conversion coefficients. 1185001100007 (ERR-1) Neutron flux, 10% 1185001100008 (ERR-2,,6.) Gamma-ray attenuation by the samples 1185001100009 (ERR-3) Brief variations in flux, 2.5% 1185001100010 (ERR-4,,3.) Uncertainty in the reported half-lives 1185001100011 (ERR-5,,3.5) Non-reproducibility of irradiation and 1185001100012 delay times 1185001100013 (ERR-6) Counting efficiency 3.5% 1185001100014 (ERR-7) Fractional photopeak efficiency, 2.5% 1185001100015 (ERR-S,0.5,8.2) Statistical error in gamma counting, 1185001100016 on average 1.4% 1185001100017 (ERR-8,,0.5) Interference of (n,g) reactions by 1185001100018 thermal neutrons. 1185001100019 HISTORY (19860206A) Reaction corrected. 1185001100020 (20220814A) REACTION SF4 changed to M1, added SF5 1185001100021 ENDBIB 19 0 1185001100022 COMMON 4 3 1185001100023 ERR-1 ERR-3 ERR-6 ERR-7 1185001100024 PER-CENT PER-CENT PER-CENT PER-CENT 1185001100025 10. 2.5 3.5 2.5 1185001100026 ENDCOMMON 3 0 1185001100027 DATA 4 1 1185001100028 EN EN-RSL DATA ERR-T 1185001100029 MEV MEV B PER-CENT 1185001100030 2.80 +00 7. -02 5.10 -01 13. 1185001100031 ENDDATA 3 0 1185001100032 ENDSUBENT 31 0 1185001199999 SUBENT 11850012 20220822 15001185001200001 BIB 4 18 1185001200002 REACTION (80-HG-199(N,INL)80-HG-199-M,,SIG) 1185001200003 DECAY-DATA (80-HG-199-M,44.MIN,DG/ICE,370.,1.0) 1185001200004 ERR-ANALYS (ERR-T) Quoted errors include the following sources 1185001200005 of uncertainties. Not included are uncertainties of 1185001200006 decay schemes and conversion coefficients. 1185001200007 (ERR-1) Neutron flux, 10% 1185001200008 (ERR-2,,6.) Gamma-ray attenuation by the samples 1185001200009 (ERR-3) Brief variations in flux, 2.5% 1185001200010 (ERR-4,,3.) Uncertainty in the reported half-lives 1185001200011 (ERR-5,,3.5) Non-reproducibility of irradiation and 1185001200012 delay times 1185001200013 (ERR-6) Counting efficiency 3.5% 1185001200014 (ERR-7) Fractional photopeak efficiency, 2.5% 1185001200015 (ERR-S,0.5,8.2) Statistical error in gamma counting, 1185001200016 on average 1.4% 1185001200017 (ERR-8,,0.5) Interference of (n,g) reactions by 1185001200018 thermal neutrons. 1185001200019 HISTORY (19860206A) Reaction corrected. 1185001200020 ENDBIB 18 0 1185001200021 COMMON 4 3 1185001200022 ERR-1 ERR-3 ERR-6 ERR-7 1185001200023 PER-CENT PER-CENT PER-CENT PER-CENT 1185001200024 10. 2.5 3.5 2.5 1185001200025 ENDCOMMON 3 0 1185001200026 DATA 4 1 1185001200027 EN EN-RSL DATA ERR-T 1185001200028 MEV MEV B PER-CENT 1185001200029 2.80 +00 7. -02 9.5 -02 13. 1185001200030 ENDDATA 3 0 1185001200031 ENDSUBENT 30 0 1185001299999 SUBENT 11850013 20220822 15001185001300001 BIB 4 18 1185001300002 REACTION (34-SE-77(N,INL)34-SE-77-M,,SIG) 1185001300003 DECAY-DATA (34-SE-77-M,17.5SEC,DG/ICE,161.,1.0) 1185001300004 ERR-ANALYS (ERR-T) Quoted errors include the following sources 1185001300005 of uncertainties. Not included are uncertainties of 1185001300006 decay schemes and conversion coefficients. 1185001300007 (ERR-1) Neutron flux, 10% 1185001300008 (ERR-2,,6.) Gamma-ray attenuation by the samples 1185001300009 (ERR-3) Brief variations in flux, 2.5% 1185001300010 (ERR-4,,3.) Uncertainty in the reported half-lives 1185001300011 (ERR-5,,3.5) Non-reproducibility of irradiation and 1185001300012 delay times 1185001300013 (ERR-6) Counting efficiency 3.5% 1185001300014 (ERR-7) Fractional photopeak efficiency, 2.5% 1185001300015 (ERR-S,0.5,8.2) Statistical error in gamma counting, 1185001300016 on average 1.4% 1185001300017 (ERR-8,,0.5) Interference of (n,g) reactions by 1185001300018 thermal neutrons. 1185001300019 HISTORY (19860206A) Reaction corrected. 1185001300020 ENDBIB 18 0 1185001300021 COMMON 4 3 1185001300022 ERR-1 ERR-3 ERR-6 ERR-7 1185001300023 PER-CENT PER-CENT PER-CENT PER-CENT 1185001300024 10. 2.5 3.5 2.5 1185001300025 ENDCOMMON 3 0 1185001300026 DATA 4 1 1185001300027 EN EN-RSL DATA ERR-T 1185001300028 MEV MEV B PER-CENT 1185001300029 2.8 +00 7. -02 1.0 13. 1185001300030 ENDDATA 3 0 1185001300031 ENDSUBENT 30 0 1185001399999 SUBENT 11850014 20220822 15001185001400001 BIB 4 18 1185001400002 REACTION (35-BR-79(N,INL)35-BR-79-M,,SIG) 1185001400003 DECAY-DATA (35-BR-79-M,4.8SEC,DG,208.,1.0) 1185001400004 ERR-ANALYS (ERR-T) Quoted errors include the following sources 1185001400005 of uncertainties. Not included are uncertainties of 1185001400006 decay schemes and conversion coefficients. 1185001400007 (ERR-1) Neutron flux, 10% 1185001400008 (ERR-2,,6.) Gamma-ray attenuation by the samples 1185001400009 (ERR-3) Brief variations in flux, 2.5% 1185001400010 (ERR-4,,3.) Uncertainty in the reported half-lives 1185001400011 (ERR-5,,3.5) Non-reproducibility of irradiation and 1185001400012 delay times 1185001400013 (ERR-6) Counting efficiency 3.5% 1185001400014 (ERR-7) Fractional photopeak efficiency, 2.5% 1185001400015 (ERR-S,0.5,8.2) Statistical error in gamma counting, 1185001400016 on average 1.4% 1185001400017 (ERR-8,,0.5) Interference of (n,g) reactions by 1185001400018 thermal neutrons. 1185001400019 HISTORY (19860206A) Reaction corrected. 1185001400020 ENDBIB 18 0 1185001400021 COMMON 4 3 1185001400022 ERR-1 ERR-3 ERR-6 ERR-7 1185001400023 PER-CENT PER-CENT PER-CENT PER-CENT 1185001400024 10. 2.5 3.5 2.5 1185001400025 ENDCOMMON 3 0 1185001400026 DATA 4 1 1185001400027 EN EN-RSL DATA ERR-T 1185001400028 MEV MEV B PER-CENT 1185001400029 2.8 +00 7. -02 2.37 -01 13. 1185001400030 ENDDATA 3 0 1185001400031 ENDSUBENT 30 0 1185001499999 ENDENTRY 14 0 1185099999999