ENTRY 13586 20090928 13571358600000001 SUBENT 13586001 20090928 13571358600100001 BIB 10 25 1358600100002 INSTITUTE (1USAANL,1USALAS,2JPNJAE) 1358600100003 REFERENCE (J,ANE,23,877,199607) 1358600100004 AUTHOR (J.W.Meadows,D.L.Smith,L.R.Greenwood,R.C.Haight, 1358600100005 Y.Ikeda,C.Konno) 1358600100006 TITLE Measurement of fast-neutron activation cross sections 1358600100007 for copper, europium, hafnium, iron, nickel, silver, 1358600100008 terbium and titanium at 10.0 and 14.7 MeV and for the 1358600100009 Be(d,n) thick-target spectrum. 1358600100010 METHOD (ACTIV) 1358600100011 DETECTOR (GE-IN) Gamma-ray activity measured at anl using 1358600100012 intrinsic germanium detectors. 1358600100013 MONITOR (28-NI-58(N,P)27-CO-58,,SIG) 1358600100014 CORRECTION Corrected for: 1358600100015 . detector efficiency, 1358600100016 . neutron multiple scattering, 1358600100017 . sum-coincidence losses, 1358600100018 . sample counting geometry, 1358600100019 . sample absorption, 1358600100020 . decay branching factors. 1358600100021 STATUS (TABLE) Data taken from tables in article. 1358600100022 (APRVD) Approved by D. L. Smith, 1996/8/2. 1358600100023 (COREL,22657001) Results from JAERI measurement. 1358600100024 HISTORY (19960702C) 1358600100025 (20090928A) VM:Updated to new date formats,lower case. 1358600100026 BIB Updates. 1358600100027 ENDBIB 25 0 1358600100028 NOCOMMON 0 0 1358600100029 ENDSUBENT 28 0 1358600199999 SUBENT 13586002 20090928 13571358600200001 BIB 8 20 1358600200002 REACTION ((22-TI-46(N,P)21-SC-46,,SIG)+ 1358600200003 (22-TI-47(N,X)21-SC-46,,SIG,,RAB)) 1358600200004 Data for natural element divided by 46Ti abundance. 1358600200005 SAMPLE Elemental sample 1358600200006 DECAY-DATA (21-SC-46-G,83.810D,DG,889.,0.99984) 1358600200007 (21-SC-46-M,18.75SEC) 1358600200008 FACILITY (VDGT,1USALAS) 1358600200009 INC-SOURCE (P-T) 16.55-MeV triton beam on rotating H-gas target. 1358600200010 CORRECTION Also corrected for 1358600200011 - fission-deposit thickness losses 1358600200012 - irradiation-geometry effects 1358600200013 - perturbations due to neutron scattering in the 1358600200014 irradiation environment 1358600200015 - for neutrons outside primary neutron-energy group 1358600200016 ERR-ANALYS (EN-ERR) Uncertainty in calculating the energy lost by 1358600200017 tritons in passing through the Mo entrance window and 1358600200018 filler gas of the target cell. 1358600200019 (ERR-T) absolute uncertainty. See table 7 in article 1358600200020 for contributions. 1358600200021 HISTORY (20090928A) Reaction corrected. 1358600200022 ENDBIB 20 0 1358600200023 COMMON 5 3 1358600200024 EN EN-ERR EN-RSL MONIT MONIT-ERR 1358600200025 MEV MEV MEV MB MB 1358600200026 10.0 0.2 0.6 613. 32. 1358600200027 ENDCOMMON 3 0 1358600200028 DATA 2 1 1358600200029 DATA ERR-T 1358600200030 MB PER-CENT 1358600200031 275. 13.0 1358600200032 ENDDATA 3 0 1358600200033 ENDSUBENT 32 0 1358600299999 SUBENT 13586003 20090928 13571358600300001 BIB 7 16 1358600300002 REACTION (26-FE-54(N,P)25-MN-54,,SIG) 1358600300003 SAMPLE Elemental sample 1358600300004 DECAY-DATA (25-MN-54,312.12D,DG,835.,0.99976) 1358600300005 FACILITY (VDGT,1USALAS) 1358600300006 INC-SOURCE (P-T) 16.55-MeV triton beam on rotating H-gas target. 1358600300007 CORRECTION Also corrected for 1358600300008 - fission-deposit thickness losses 1358600300009 - irradiation-geometry effects 1358600300010 - perturbations due to neutron scattering in the 1358600300011 irradiation environment 1358600300012 - for neutrons outside primary neutron-energy group 1358600300013 ERR-ANALYS (EN-ERR) Uncertainty in calculating the energy lost by 1358600300014 tritons in passing through the Mo entrance window and 1358600300015 filler gas of the target cell. 1358600300016 (ERR-T) absolute uncertainty. See table 7 in article 1358600300017 for contributions. 1358600300018 ENDBIB 16 0 1358600300019 COMMON 5 3 1358600300020 EN EN-ERR EN-RSL MONIT MONIT-ERR 1358600300021 MEV MEV MEV MB MB 1358600300022 10.0 0.2 0.6 613. 32. 1358600300023 ENDCOMMON 3 0 1358600300024 DATA 2 1 1358600300025 DATA ERR-T 1358600300026 MB PER-CENT 1358600300027 499. 6.8 1358600300028 ENDDATA 3 0 1358600300029 ENDSUBENT 28 0 1358600399999 SUBENT 13586004 20090928 13571358600400001 BIB 7 16 1358600400002 REACTION (26-FE-54(N,A)24-CR-51,,SIG) 1358600400003 SAMPLE Elemental sample 1358600400004 DECAY-DATA (24-CR-51,27.702D,DG,320.,0.1008) 1358600400005 FACILITY (VDGT,1USALAS) 1358600400006 INC-SOURCE (P-T) 16.55-MeV triton beam on rotating H-gas target. 1358600400007 CORRECTION Also corrected for 1358600400008 - fission-deposit thickness losses 1358600400009 - irradiation-geometry effects 1358600400010 - perturbations due to neutron scattering in the 1358600400011 irradiation environment 1358600400012 - for neutrons outside primary neutron-energy group 1358600400013 ERR-ANALYS (EN-ERR) Uncertainty in calculating the energy lost by 1358600400014 tritons in passing through the Mo entrance window and 1358600400015 filler gas of the target cell. 1358600400016 (ERR-T) absolute uncertainty. See table 7 in article 1358600400017 for contributions. 1358600400018 ENDBIB 16 0 1358600400019 COMMON 5 3 1358600400020 EN EN-ERR EN-RSL MONIT MONIT-ERR 1358600400021 MEV MEV MEV MB MB 1358600400022 10.0 0.2 0.6 613. 32. 1358600400023 ENDCOMMON 3 0 1358600400024 DATA 2 1 1358600400025 DATA ERR-T 1358600400026 MB PER-CENT 1358600400027 40.8 9.0 1358600400028 ENDDATA 3 0 1358600400029 ENDSUBENT 28 0 1358600499999 SUBENT 13586005 20090928 13571358600500001 BIB 7 17 1358600500002 REACTION (29-CU-63(N,A)27-CO-60,,SIG) 1358600500003 SAMPLE Elemental sample 1358600500004 DECAY-DATA (27-CO-60-G,5.2714YR,DG,1333.,0.99982) 1358600500005 (27-CO-60-M,10.47MIN) 1358600500006 FACILITY (VDGT,1USALAS) 1358600500007 INC-SOURCE (P-T) 16.55-MeV triton beam on rotating H-gas target. 1358600500008 CORRECTION Also corrected for 1358600500009 - fission-deposit thickness losses 1358600500010 - irradiation-geometry effects 1358600500011 - perturbations due to neutron scattering in the 1358600500012 irradiation environment 1358600500013 - for neutrons outside primary neutron-energy group 1358600500014 ERR-ANALYS (EN-ERR) Uncertainty in calculating the energy lost by 1358600500015 tritons in passing through the Mo entrance window and 1358600500016 filler gas of the target cell. 1358600500017 (ERR-T) absolute uncertainty. See table 7 in article 1358600500018 for contributions. 1358600500019 ENDBIB 17 0 1358600500020 COMMON 5 3 1358600500021 EN EN-ERR EN-RSL MONIT MONIT-ERR 1358600500022 MEV MEV MEV MB MB 1358600500023 10.0 0.2 0.6 613. 32. 1358600500024 ENDCOMMON 3 0 1358600500025 DATA 2 1 1358600500026 DATA ERR-T 1358600500027 MB PER-CENT 1358600500028 29.3 8.1 1358600500029 ENDDATA 3 0 1358600500030 ENDSUBENT 29 0 1358600599999 SUBENT 13586006 20090928 13571358600600001 BIB 7 16 1358600600002 REACTION (47-AG-107(N,2N)47-AG-106-M,,SIG) 1358600600003 SAMPLE Elemental sample 1358600600004 DECAY-DATA (47-AG-106-M,8.46D,DG,512.,0.877) 1358600600005 FACILITY (VDGT,1USALAS) 1358600600006 INC-SOURCE (P-T) 16.55-MeV triton beam on rotating H-gas target. 1358600600007 CORRECTION Also corrected for 1358600600008 - fission-deposit thickness losses 1358600600009 - irradiation-geometry effects 1358600600010 - perturbations due to neutron scattering in the 1358600600011 irradiation environment 1358600600012 - for neutrons outside primary neutron-energy group 1358600600013 ERR-ANALYS (EN-ERR) Uncertainty in calculating the energy lost by 1358600600014 tritons in passing through the Mo entrance window and 1358600600015 filler gas of the target cell. 1358600600016 (ERR-T) absolute uncertainty. See table 7 in article 1358600600017 for contributions. 1358600600018 ENDBIB 16 0 1358600600019 COMMON 5 3 1358600600020 EN EN-ERR EN-RSL MONIT MONIT-ERR 1358600600021 MEV MEV MEV MB MB 1358600600022 10.0 0.2 0.6 613. 32. 1358600600023 ENDCOMMON 3 0 1358600600024 DATA 2 1 1358600600025 DATA ERR-T 1358600600026 MB PER-CENT 1358600600027 1.96 9.0 1358600600028 ENDDATA 3 0 1358600600029 ENDSUBENT 28 0 1358600699999 SUBENT 13586007 20090928 13571358600700001 BIB 7 14 1358600700002 REACTION (63-EU-151(N,2N)63-EU-150-G,,SIG) 1358600700003 SAMPLE Elemental sample 1358600700004 DECAY-DATA (63-EU-150-G,35.8YR,DG,334.,0.96) 1358600700005 FACILITY (VDGT,1USALAS) 1358600700006 INC-SOURCE (P-T) 16.55-MeV triton beam on rotating H-gas target. 1358600700007 CORRECTION Also corrected for 1358600700008 - fission-deposit thickness losses 1358600700009 - irradiation-geometry effects 1358600700010 - perturbations due to neutron scattering in the 1358600700011 irradiation environment 1358600700012 - for neutrons outside primary neutron-energy group 1358600700013 ERR-ANALYS (EN-ERR) Uncertainty in calculating the energy lost by 1358600700014 tritons in passing through the Mo entrance window and 1358600700015 filler gas of the target cell. 1358600700016 ENDBIB 14 0 1358600700017 COMMON 5 3 1358600700018 EN EN-ERR EN-RSL MONIT MONIT-ERR 1358600700019 MEV MEV MEV MB MB 1358600700020 10.0 0.2 0.6 613. 32. 1358600700021 ENDCOMMON 3 0 1358600700022 DATA 2 1 1358600700023 DATA ERR-T 1358600700024 MB PER-CENT 1358600700025 282. 11.3 1358600700026 ENDDATA 3 0 1358600700027 ENDSUBENT 26 0 1358600799999 SUBENT 13586008 20090928 13571358600800001 BIB 7 17 1358600800002 REACTION (65-TB-159(N,2N)65-TB-158,,SIG) 1358600800003 SAMPLE Elemental sample 1358600800004 DECAY-DATA (65-TB-158-G,180.YR,DG,944.,0.439) 1358600800005 (65-TB-158-M,10.5SEC) 1358600800006 FACILITY (VDGT,1USALAS) 1358600800007 INC-SOURCE (P-T) 16.55-MeV triton beam on rotating H-gas target. 1358600800008 CORRECTION Also corrected for 1358600800009 - fission-deposit thickness losses 1358600800010 - irradiation-geometry effects 1358600800011 - perturbations due to neutron scattering in the 1358600800012 irradiation environment 1358600800013 - for neutrons outside primary neutron-energy group 1358600800014 ERR-ANALYS (EN-ERR) Uncertainty in calculating the energy lost by 1358600800015 tritons in passing through the Mo entrance window and 1358600800016 filler gas of the target cell. 1358600800017 (ERR-T) absolute uncertainty. See table 7 in article 1358600800018 for contributions. 1358600800019 ENDBIB 17 0 1358600800020 COMMON 5 3 1358600800021 EN EN-ERR EN-RSL MONIT MONIT-ERR 1358600800022 MEV MEV MEV MB MB 1358600800023 10.0 0.2 0.6 613. 32. 1358600800024 ENDCOMMON 3 0 1358600800025 DATA 2 1 1358600800026 DATA ERR-T 1358600800027 MB PER-CENT 1358600800028 555. 13.9 1358600800029 ENDDATA 3 0 1358600800030 ENDSUBENT 29 0 1358600899999 SUBENT 13586009 20090928 13571358600900001 BIB 7 16 1358600900002 REACTION (72-HF-176(N,2N)72-HF-175,,SIG) 1358600900003 SAMPLE Elemental sample 1358600900004 DECAY-DATA (72-HF-175,70.D,DG,343.,0.84) 1358600900005 FACILITY (VDGT,1USALAS) 1358600900006 INC-SOURCE (P-T) 16.55-MeV triton beam on rotating H-gas target. 1358600900007 CORRECTION Also corrected for 1358600900008 - fission-deposit thickness losses 1358600900009 - irradiation-geometry effects 1358600900010 - perturbations due to neutron scattering in the 1358600900011 irradiation environment 1358600900012 - for neutrons outside primary neutron-energy group 1358600900013 ERR-ANALYS (EN-ERR) Uncertainty in calculating the energy lost by 1358600900014 tritons in passing through the Mo entrance window and 1358600900015 filler gas of the target cell. 1358600900016 (ERR-T) absolute uncertainty. See table 7 in article 1358600900017 for contributions. 1358600900018 ENDBIB 16 0 1358600900019 COMMON 5 3 1358600900020 EN EN-ERR EN-RSL MONIT MONIT-ERR 1358600900021 MEV MEV MEV MB MB 1358600900022 10.0 0.2 0.6 613. 32. 1358600900023 ENDCOMMON 3 0 1358600900024 DATA 2 1 1358600900025 DATA ERR-T 1358600900026 MB PER-CENT 1358600900027 548. 12.8 1358600900028 ENDDATA 3 0 1358600900029 ENDSUBENT 28 0 1358600999999 SUBENT 13586010 20090928 13571358601000001 BIB 8 19 1358601000002 REACTION ((72-HF-180(N,2N)72-HF-179-M2,,SIG)+ 1358601000003 (72-HF-179(N,INL)72-HF-179-M2,,SIG,,RAB)) 1358601000004 Data for natural element divided by 180Hf abundance. 1358601000005 SAMPLE Elemental sample 1358601000006 DECAY-DATA (72-HF-179-M2,25.1D,DG,454.,0.686) 1358601000007 FACILITY (VDGT,1USALAS) 1358601000008 INC-SOURCE (P-T) 16.55-MeV triton beam on rotating H-gas target. 1358601000009 CORRECTION Also corrected for 1358601000010 - fission-deposit thickness losses 1358601000011 - irradiation-geometry effects 1358601000012 - perturbations due to neutron scattering in the 1358601000013 irradiation environment 1358601000014 - for neutrons outside primary neutron-energy group 1358601000015 ERR-ANALYS (EN-ERR) Uncertainty in calculating the energy lost by 1358601000016 tritons in passing through the Mo entrance window and 1358601000017 filler gas of the target cell. 1358601000018 (ERR-T) absolute uncertainty. See table 7 in article 1358601000019 for contributions. 1358601000020 HISTORY (20090928A) Reaction corrected. 1358601000021 ENDBIB 19 0 1358601000022 COMMON 5 3 1358601000023 EN EN-ERR EN-RSL MONIT MONIT-ERR 1358601000024 MEV MEV MEV MB MB 1358601000025 10.0 0.2 0.6 613. 32. 1358601000026 ENDCOMMON 3 0 1358601000027 DATA 2 1 1358601000028 DATA ERR-T 1358601000029 MB PER-CENT 1358601000030 11.2 10.3 1358601000031 ENDDATA 3 0 1358601000032 ENDSUBENT 31 0 1358601099999 SUBENT 13586011 20090928 13571358601100001 BIB 6 15 1358601100002 REACTION (92-U-238(N,F),,SIG) 1358601100003 SAMPLE Depleted uranium sample (99.585% 238U, 0.415% 235U). 1358601100004 FACILITY (VDGT,1USALAS) 1358601100005 INC-SOURCE (P-T) 16.55-MeV triton beam on rotating H-gas target. 1358601100006 CORRECTION Also corrected for 1358601100007 - fission-deposit thickness losses 1358601100008 - irradiation-geometry effects 1358601100009 - perturbations due to neutron scattering in the 1358601100010 irradiation environment 1358601100011 - for neutrons outside primary neutron-energy group 1358601100012 ERR-ANALYS (EN-ERR) Uncertainty in calculating the energy lost by 1358601100013 tritons in passing through the Mo entrance window and 1358601100014 filler gas of the target cell. 1358601100015 (ERR-T) absolute uncertainty. See table 7 in article 1358601100016 for contributions. 1358601100017 ENDBIB 15 0 1358601100018 COMMON 5 3 1358601100019 EN EN-ERR EN-RSL MONIT MONIT-ERR 1358601100020 MEV MEV MEV MB MB 1358601100021 10.0 0.2 0.6 613. 32. 1358601100022 ENDCOMMON 3 0 1358601100023 DATA 2 1 1358601100024 DATA ERR-T 1358601100025 MB PER-CENT 1358601100026 1115. 8.2 1358601100027 ENDDATA 3 0 1358601100028 ENDSUBENT 27 0 1358601199999 SUBENT 13586012 20090928 13571358601200001 BIB 8 14 1358601200002 REACTION ((22-TI-46(N,P)21-SC-46,,SIG)+ 1358601200003 (22-TI-47(N,X)21-SC-46,,SIG,,RAB)) 1358601200004 Data for natural element divided by 46Ti abundance. 1358601200005 SAMPLE Elemental sample 1358601200006 DECAY-DATA (21-SC-46-G,83.810D,DG,889.,0.99984) 1358601200007 (21-SC-46-M,18.75SEC) 1358601200008 FACILITY (CCW,2JPNJAE) JAERI fusion neutronics source 1358601200009 INC-SOURCE (D-T) 350-keV deuterons on a rotating titanium-tritide 1358601200010 target. 1358601200011 CORRECTION Also corrected for 1358601200012 - for neutrons outside primary neutron-energy group 1358601200013 ERR-ANALYS (ERR-T) absolute uncertainty. See table 8 in article 1358601200014 for contributions. 1358601200015 HISTORY (20090928A) Reaction corrected. Data error corrected. 1358601200016 ENDBIB 14 0 1358601200017 COMMON 4 3 1358601200018 EN EN-RSL MONIT MONIT-ERR 1358601200019 MEV MEV MB MB 1358601200020 14.7 0.5 292. 14. 1358601200021 ENDCOMMON 3 0 1358601200022 DATA 2 1 1358601200023 DATA ERR-T 1358601200024 MB PER-CENT 1358601200025 306. 5.5 1358601200026 ENDDATA 3 0 1358601200027 ENDSUBENT 26 0 1358601299999 SUBENT 13586013 20090928 13571358601300001 BIB 7 10 1358601300002 REACTION (26-FE-54(N,P)25-MN-54,,SIG) 1358601300003 SAMPLE Elemental sample 1358601300004 DECAY-DATA (25-MN-54,312.12D,DG,835.,0.99976) 1358601300005 FACILITY (CCW,2JPNJAE) JAERI fusion neutronics source 1358601300006 INC-SOURCE (D-T) 350-keV deuterons on a rotating titanium-tritide 1358601300007 target. 1358601300008 CORRECTION Also corrected for 1358601300009 - for neutrons outside primary neutron-energy group 1358601300010 ERR-ANALYS (ERR-T) absolute uncertainty. See table 8 in article 1358601300011 for contributions. 1358601300012 ENDBIB 10 0 1358601300013 COMMON 4 3 1358601300014 EN EN-RSL MONIT MONIT-ERR 1358601300015 MEV MEV MB MB 1358601300016 14.7 0.5 292. 14. 1358601300017 ENDCOMMON 3 0 1358601300018 DATA 2 1 1358601300019 DATA ERR-T 1358601300020 MB PER-CENT 1358601300021 280. 6.4 1358601300022 ENDDATA 3 0 1358601300023 ENDSUBENT 22 0 1358601399999 SUBENT 13586014 20090928 13571358601400001 BIB 7 10 1358601400002 REACTION (26-FE-54(N,A)24-CR-51,,SIG) 1358601400003 SAMPLE Elemental sample 1358601400004 DECAY-DATA (24-CR-51,27.702D,DG,320.,0.1008) 1358601400005 FACILITY (CCW,2JPNJAE) JAERI fusion neutronics source 1358601400006 INC-SOURCE (D-T) 350-keV deuterons on a rotating titanium-tritide 1358601400007 target. 1358601400008 CORRECTION Also corrected for 1358601400009 - for neutrons outside primary neutron-energy group 1358601400010 ERR-ANALYS (ERR-T) absolute uncertainty. See table 8 in article 1358601400011 for contributions. 1358601400012 ENDBIB 10 0 1358601400013 COMMON 4 3 1358601400014 EN EN-RSL MONIT MONIT-ERR 1358601400015 MEV MEV MB MB 1358601400016 14.7 0.5 292. 14. 1358601400017 ENDCOMMON 3 0 1358601400018 DATA 2 1 1358601400019 DATA ERR-T 1358601400020 MB PER-CENT 1358601400021 87.9 6.5 1358601400022 ENDDATA 3 0 1358601400023 ENDSUBENT 22 0 1358601499999 SUBENT 13586015 20090928 13571358601500001 BIB 7 11 1358601500002 REACTION (29-CU-63(N,A)27-CO-60,,SIG) 1358601500003 SAMPLE Elemental sample 1358601500004 DECAY-DATA (27-CO-60-G,5.2714YR,DG,1333.,0.99982) 1358601500005 (27-CO-60-M,10.47MIN) 1358601500006 FACILITY (CCW,2JPNJAE) JAERI fusion neutronics source 1358601500007 INC-SOURCE (D-T) 350-keV deuterons on a rotating titanium-tritide 1358601500008 target. 1358601500009 CORRECTION Also corrected for 1358601500010 - for neutrons outside primary neutron-energy group 1358601500011 ERR-ANALYS (ERR-T) absolute uncertainty. See table 8 in article 1358601500012 for contributions. 1358601500013 ENDBIB 11 0 1358601500014 COMMON 4 3 1358601500015 EN EN-RSL MONIT MONIT-ERR 1358601500016 MEV MEV MB MB 1358601500017 14.7 0.5 292. 14. 1358601500018 ENDCOMMON 3 0 1358601500019 DATA 2 1 1358601500020 DATA ERR-T 1358601500021 MB PER-CENT 1358601500022 41.6 5.4 1358601500023 ENDDATA 3 0 1358601500024 ENDSUBENT 23 0 1358601599999 SUBENT 13586016 20090928 13571358601600001 BIB 7 10 1358601600002 REACTION (47-AG-109(N,2N)47-AG-108-M,,SIG) 1358601600003 SAMPLE Elemental sample 1358601600004 DECAY-DATA (47-AG-108-M,418.YR,DG,434.,0.905) 1358601600005 FACILITY (CCW,2JPNJAE) JAERI fusion neutronics source 1358601600006 INC-SOURCE (D-T) 350-keV deuterons on a rotating titanium-tritide 1358601600007 target. 1358601600008 CORRECTION Also corrected for 1358601600009 - for neutrons outside primary neutron-energy group 1358601600010 ERR-ANALYS (ERR-T) absolute uncertainty. See table 8 in article 1358601600011 for contributions. 1358601600012 ENDBIB 10 0 1358601600013 COMMON 4 3 1358601600014 EN EN-RSL MONIT MONIT-ERR 1358601600015 MEV MEV MB MB 1358601600016 14.7 0.5 292. 14. 1358601600017 ENDCOMMON 3 0 1358601600018 DATA 2 1 1358601600019 DATA ERR-T 1358601600020 MB PER-CENT 1358601600021 628. 6.7 1358601600022 ENDDATA 3 0 1358601600023 ENDSUBENT 22 0 1358601699999 SUBENT 13586017 20090928 13571358601700001 BIB 7 10 1358601700002 REACTION (63-EU-151(N,2N)63-EU-150-G,,SIG) 1358601700003 SAMPLE Elemental sample 1358601700004 DECAY-DATA (63-EU-150-G,35.8YR,DG,334.,0.96) 1358601700005 FACILITY (CCW,2JPNJAE) JAERI fusion neutronics source 1358601700006 INC-SOURCE (D-T) 350-keV deuterons on a rotating titanium-tritide 1358601700007 target. 1358601700008 CORRECTION Also corrected for 1358601700009 - for neutrons outside primary neutron-energy group 1358601700010 ERR-ANALYS (ERR-T) absolute uncertainty. See table 8 in article 1358601700011 for contributions. 1358601700012 ENDBIB 10 0 1358601700013 COMMON 4 3 1358601700014 EN EN-RSL MONIT MONIT-ERR 1358601700015 MEV MEV MB MB 1358601700016 14.7 0.5 292. 14. 1358601700017 ENDCOMMON 3 0 1358601700018 DATA 2 1 1358601700019 DATA ERR-T 1358601700020 MB PER-CENT 1358601700021 1214. 7.7 1358601700022 ENDDATA 3 0 1358601700023 ENDSUBENT 22 0 1358601799999 SUBENT 13586018 20090928 13571358601800001 BIB 7 11 1358601800002 REACTION (65-TB-159(N,2N)65-TB-158,,SIG) 1358601800003 SAMPLE Elemental sample 1358601800004 DECAY-DATA (65-TB-158-G,180.YR,DG,944.,0.439) 1358601800005 (65-TB-158-M,10.5SEC) 1358601800006 FACILITY (CCW,2JPNJAE) JAERI fusion neutronics source 1358601800007 INC-SOURCE (D-T) 350-keV deuterons on a rotating titanium-tritide 1358601800008 target. 1358601800009 CORRECTION Also corrected for 1358601800010 - for neutrons outside primary neutron-energy group 1358601800011 ERR-ANALYS (ERR-T) absolute uncertainty. See table 8 in article 1358601800012 for contributions. 1358601800013 ENDBIB 11 0 1358601800014 COMMON 4 3 1358601800015 EN EN-RSL MONIT MONIT-ERR 1358601800016 MEV MEV MB MB 1358601800017 14.7 0.5 292. 14. 1358601800018 ENDCOMMON 3 0 1358601800019 DATA 2 1 1358601800020 DATA ERR-T 1358601800021 MB PER-CENT 1358601800022 1981. 9.3 1358601800023 ENDDATA 3 0 1358601800024 ENDSUBENT 23 0 1358601899999 SUBENT 13586019 20090928 13571358601900001 BIB 7 10 1358601900002 REACTION (72-HF-176(N,2N)72-HF-175,,SIG) 1358601900003 SAMPLE Elemental sample 1358601900004 DECAY-DATA (72-HF-175,70.D,DG,343.,0.84) 1358601900005 FACILITY (CCW,2JPNJAE) JAERI fusion neutronics source 1358601900006 INC-SOURCE (D-T) 350-keV deuterons on a rotating titanium-tritide 1358601900007 target. 1358601900008 CORRECTION Also corrected for 1358601900009 - for neutrons outside primary neutron-energy group 1358601900010 ERR-ANALYS (ERR-T) absolute uncertainty. See table 8 in article 1358601900011 for contributions. 1358601900012 ENDBIB 10 0 1358601900013 COMMON 4 3 1358601900014 EN EN-RSL MONIT MONIT-ERR 1358601900015 MEV MEV MB MB 1358601900016 14.7 0.5 292. 14. 1358601900017 ENDCOMMON 3 0 1358601900018 DATA 2 1 1358601900019 DATA ERR-T 1358601900020 MB PER-CENT 1358601900021 1915. 7.9 1358601900022 ENDDATA 3 0 1358601900023 ENDSUBENT 22 0 1358601999999 SUBENT 13586020 20090928 13571358602000001 BIB 8 13 1358602000002 REACTION ((72-HF-180(N,2N)72-HF-179-M2,,SIG)+ 1358602000003 (72-HF-179(N,INL)72-HF-179-M2,,SIG,,RAB)) 1358602000004 Data for natural element divided by 180Hf abundance. 1358602000005 SAMPLE Elemental sample 1358602000006 DECAY-DATA (72-HF-179-M2,25.1D,DG,454.,0.686) 1358602000007 FACILITY (CCW,2JPNJAE) JAERI fusion neutronics source 1358602000008 INC-SOURCE (D-T) 350-keV deuterons on a rotating titanium-tritide 1358602000009 target. 1358602000010 CORRECTION Also corrected for 1358602000011 - for neutrons outside primary neutron-energy group 1358602000012 ERR-ANALYS (ERR-T) absolute uncertainty. See table 8 in article 1358602000013 for contributions. 1358602000014 HISTORY (20090928A) Reaction corrected. 1358602000015 ENDBIB 13 0 1358602000016 COMMON 4 3 1358602000017 EN EN-RSL MONIT MONIT-ERR 1358602000018 MEV MEV MB MB 1358602000019 14.7 0.5 292. 14. 1358602000020 ENDCOMMON 3 0 1358602000021 DATA 2 1 1358602000022 DATA ERR-T 1358602000023 MB PER-CENT 1358602000024 21.8 8.6 1358602000025 ENDDATA 3 0 1358602000026 ENDSUBENT 25 0 1358602099999 SUBENT 13586021 20090928 13571358602100001 BIB 9 14 1358602100002 REACTION (22-TI-46(N,P)21-SC-46,,SIG,,SPA) 1358602100003 SAMPLE Elemental sample 1358602100004 DECAY-DATA (21-SC-46-G,83.810D,DG,889.,0.99984) 1358602100005 (21-SC-46-M,18.75SEC) 1358602100006 FACILITY (DYNAM,1USAANL) ANL fast neutron generator accelerator 1358602100007 INC-SOURCE (D-BE) 7-MeV deuterons on 0.15-cm-thick Be metal target1358602100008 INC-SPECT Neutron spectrum of <0.2 MeV to about 11.4 MeV. 1358602100009 METHOD Sample irradiated for about 110 hours. 1358602100010 Relative flux monitored by long counter. 1358602100011 CORRECTION Also corrected for 1358602100012 - decay of sample radioactivities during irradiation 1358602100013 period 1358602100014 ERR-ANALYS (ERR-T) absolute uncertainty. See table 6 in article 1358602100015 for contributions. 1358602100016 ENDBIB 14 0 1358602100017 COMMON 4 3 1358602100018 EN-MIN EN-MAX MONIT MONIT-ERR 1358602100019 MEV MEV MB MB 1358602100020 0.2 11.4 231. 14. 1358602100021 ENDCOMMON 3 0 1358602100022 DATA 2 1 1358602100023 DATA ERR-T 1358602100024 MB PER-CENT 1358602100025 36.3 6.6 1358602100026 ENDDATA 3 0 1358602100027 ENDSUBENT 26 0 1358602199999 SUBENT 13586022 20090928 13571358602200001 BIB 9 13 1358602200002 REACTION (26-FE-54(N,P)25-MN-54,,SIG,,SPA) 1358602200003 SAMPLE Elemental sample 1358602200004 DECAY-DATA (25-MN-54,312.12D,DG,835.,0.99976) 1358602200005 FACILITY (DYNAM,1USAANL) ANL fast neutron generator accelerator 1358602200006 INC-SOURCE (D-BE) 7-MeV deuterons on 0.15-cm-thick Be metal target1358602200007 INC-SPECT Neutron spectrum of <0.2 MeV to about 11.4 MeV. 1358602200008 METHOD Sample irradiated for about 110 hours. 1358602200009 Relative flux monitored by long counter. 1358602200010 CORRECTION Also corrected for 1358602200011 - decay of sample radioactivities during irradiation 1358602200012 period 1358602200013 ERR-ANALYS (ERR-T) absolute uncertainty. See table 6 in article 1358602200014 for contributions. 1358602200015 ENDBIB 13 0 1358602200016 COMMON 4 3 1358602200017 EN-MIN EN-MAX MONIT MONIT-ERR 1358602200018 MEV MEV MB MB 1358602200019 0.2 11.4 231. 14. 1358602200020 ENDCOMMON 3 0 1358602200021 DATA 2 1 1358602200022 DATA ERR-T 1358602200023 MB PER-CENT 1358602200024 174. 7.4 1358602200025 ENDDATA 3 0 1358602200026 ENDSUBENT 25 0 1358602299999 SUBENT 13586023 20090928 13571358602300001 BIB 9 13 1358602300002 REACTION (26-FE-54(N,A)24-CR-51,,SIG,,SPA) 1358602300003 SAMPLE Elemental sample 1358602300004 DECAY-DATA (24-CR-51,27.702D,DG,320.,0.1008) 1358602300005 FACILITY (DYNAM,1USAANL) ANL fast neutron generator accelerator 1358602300006 INC-SOURCE (D-BE) 7-MeV deuterons on 0.15-cm-thick Be metal target1358602300007 INC-SPECT Neutron spectrum of <0.2 MeV to about 11.4 MeV. 1358602300008 METHOD Sample irradiated for about 110 hours. 1358602300009 Relative flux monitored by long counter. 1358602300010 CORRECTION Also corrected for 1358602300011 - decay of sample radioactivities during irradiation 1358602300012 period 1358602300013 ERR-ANALYS (ERR-T) absolute uncertainty. See table 6 in article 1358602300014 for contributions. 1358602300015 ENDBIB 13 0 1358602300016 COMMON 4 3 1358602300017 EN-MIN EN-MAX MONIT MONIT-ERR 1358602300018 MEV MEV MB MB 1358602300019 0.2 11.4 231. 14. 1358602300020 ENDCOMMON 3 0 1358602300021 DATA 2 1 1358602300022 DATA ERR-T 1358602300023 MB PER-CENT 1358602300024 3.52 7.9 1358602300025 ENDDATA 3 0 1358602300026 ENDSUBENT 25 0 1358602399999 SUBENT 13586024 20090928 13571358602400001 BIB 9 14 1358602400002 REACTION (29-CU-63(N,A)27-CO-60,,SIG,,SPA) 1358602400003 SAMPLE Elemental sample 1358602400004 DECAY-DATA (27-CO-60-G,5.2714YR,DG,1333.,0.99982) 1358602400005 (27-CO-60-M,10.47MIN) 1358602400006 FACILITY (DYNAM,1USAANL) ANL fast neutron generator accelerator 1358602400007 INC-SOURCE (D-BE) 7-MeV deuterons on 0.15-cm-thick Be metal target1358602400008 INC-SPECT Neutron spectrum of <0.2 MeV to about 11.4 MeV. 1358602400009 METHOD Sample irradiated for about 110 hours. 1358602400010 Relative flux monitored by long counter. 1358602400011 CORRECTION Also corrected for 1358602400012 - decay of sample radioactivities during irradiation 1358602400013 period 1358602400014 ERR-ANALYS (ERR-T) absolute uncertainty. See table 6 in article 1358602400015 for contributions. 1358602400016 ENDBIB 14 0 1358602400017 COMMON 4 3 1358602400018 EN-MIN EN-MAX MONIT MONIT-ERR 1358602400019 MEV MEV MB MB 1358602400020 0.2 11.4 231. 14. 1358602400021 ENDCOMMON 3 0 1358602400022 DATA 2 1 1358602400023 DATA ERR-T 1358602400024 MB PER-CENT 1358602400025 2.11 6.9 1358602400026 ENDDATA 3 0 1358602400027 ENDSUBENT 26 0 1358602499999 SUBENT 13586025 20090928 13571358602500001 BIB 9 13 1358602500002 REACTION (47-AG-107(N,2N)47-AG-106-M,,SIG,,SPA) 1358602500003 SAMPLE Elemental sample 1358602500004 DECAY-DATA (47-AG-106-M,8.46D,DG,512.,0.877) 1358602500005 FACILITY (DYNAM,1USAANL) ANL fast neutron generator accelerator 1358602500006 INC-SOURCE (D-BE) 7-MeV deuterons on 0.15-cm-thick Be metal target1358602500007 INC-SPECT Neutron spectrum of <0.2 MeV to about 11.4 MeV. 1358602500008 METHOD Sample irradiated for about 110 hours. 1358602500009 Relative flux monitored by long counter. 1358602500010 CORRECTION Also corrected for 1358602500011 - decay of sample radioactivities during irradiation 1358602500012 period 1358602500013 ERR-ANALYS (ERR-T) absolute uncertainty. See table 6 in article 1358602500014 for contributions. 1358602500015 ENDBIB 13 0 1358602500016 COMMON 4 3 1358602500017 EN-MIN EN-MAX MONIT MONIT-ERR 1358602500018 MEV MEV MB MB 1358602500019 0.2 11.4 231. 14. 1358602500020 ENDCOMMON 3 0 1358602500021 DATA 2 1 1358602500022 DATA ERR-T 1358602500023 MB PER-CENT 1358602500024 1.01 12.9 1358602500025 ENDDATA 3 0 1358602500026 ENDSUBENT 25 0 1358602599999 SUBENT 13586026 20090928 13571358602600001 BIB 9 13 1358602600002 REACTION (63-EU-151(N,2N)63-EU-150-G,,SIG,,SPA) 1358602600003 SAMPLE Elemental sample 1358602600004 DECAY-DATA (63-EU-150-G,35.8YR,DG,334.,0.96) 1358602600005 FACILITY (DYNAM,1USAANL) ANL fast neutron generator accelerator 1358602600006 INC-SOURCE (D-BE) 7-MeV deuterons on 0.15-cm-thick Be metal target1358602600007 INC-SPECT Neutron spectrum of <0.2 MeV to about 11.4 MeV. 1358602600008 METHOD Sample irradiated for about 110 hours. 1358602600009 Relative flux monitored by long counter. 1358602600010 CORRECTION Also corrected for 1358602600011 - decay of sample radioactivities during irradiation 1358602600012 period 1358602600013 ERR-ANALYS (ERR-T) absolute uncertainty. See table 6 in article 1358602600014 for contributions. 1358602600015 ENDBIB 13 0 1358602600016 COMMON 4 3 1358602600017 EN-MIN EN-MAX MONIT MONIT-ERR 1358602600018 MEV MEV MB MB 1358602600019 0.2 11.4 231. 14. 1358602600020 ENDCOMMON 3 0 1358602600021 DATA 2 1 1358602600022 DATA ERR-T 1358602600023 MB PER-CENT 1358602600024 14.8 9.3 1358602600025 ENDDATA 3 0 1358602600026 ENDSUBENT 25 0 1358602699999 SUBENT 13586027 20090928 13571358602700001 BIB 9 14 1358602700002 REACTION (65-TB-159(N,2N)65-TB-158,,SIG,,SPA) 1358602700003 SAMPLE Elemental sample 1358602700004 DECAY-DATA (65-TB-158-G,180.YR,DG,944.,0.439) 1358602700005 (65-TB-158-M,10.5SEC) 1358602700006 FACILITY (DYNAM,1USAANL) ANL fast neutron generator accelerator 1358602700007 INC-SOURCE (D-BE) 7-MeV deuterons on 0.15-cm-thick Be metal target1358602700008 INC-SPECT Neutron spectrum of <0.2 MeV to about 11.4 MeV. 1358602700009 METHOD Sample irradiated for about 110 hours. 1358602700010 Relative flux monitored by long counter. 1358602700011 CORRECTION Also corrected for 1358602700012 - decay of sample radioactivities during irradiation 1358602700013 period 1358602700014 ERR-ANALYS (ERR-T) absolute uncertainty. See table 6 in article 1358602700015 for contributions. 1358602700016 ENDBIB 14 0 1358602700017 COMMON 4 3 1358602700018 EN-MIN EN-MAX MONIT MONIT-ERR 1358602700019 MEV MEV MB MB 1358602700020 0.2 11.4 231. 14. 1358602700021 ENDCOMMON 3 0 1358602700022 DATA 2 1 1358602700023 DATA ERR-T 1358602700024 MB PER-CENT 1358602700025 27.5 12.1 1358602700026 ENDDATA 3 0 1358602700027 ENDSUBENT 26 0 1358602799999 SUBENT 13586028 20090928 13571358602800001 BIB 9 13 1358602800002 REACTION (72-HF-176(N,2N)72-HF-175,,SIG,,SPA) 1358602800003 SAMPLE Elemental sample 1358602800004 DECAY-DATA (72-HF-175,70.D,DG,343.,0.84) 1358602800005 FACILITY (DYNAM,1USAANL) ANL fast neutron generator accelerator 1358602800006 INC-SOURCE (D-BE) 7-MeV deuterons on 0.15-cm-thick Be metal target1358602800007 INC-SPECT Neutron spectrum of <0.2 MeV to about 11.4 MeV. 1358602800008 METHOD Sample irradiated for about 110 hours. 1358602800009 Relative flux monitored by long counter. 1358602800010 CORRECTION Also corrected for 1358602800011 - decay of sample radioactivities during irradiation 1358602800012 period 1358602800013 ERR-ANALYS (ERR-T) absolute uncertainty. See table 6 in article 1358602800014 for contributions. 1358602800015 ENDBIB 13 0 1358602800016 COMMON 4 3 1358602800017 EN-MIN EN-MAX MONIT MONIT-ERR 1358602800018 MEV MEV MB MB 1358602800019 0.2 11.4 231. 14. 1358602800020 ENDCOMMON 3 0 1358602800021 DATA 2 1 1358602800022 DATA ERR-T 1358602800023 MB PER-CENT 1358602800024 39.4 10.1 1358602800025 ENDDATA 3 0 1358602800026 ENDSUBENT 25 0 1358602899999 SUBENT 13586029 20090928 13571358602900001 BIB 10 16 1358602900002 REACTION ((72-HF-180(N,2N)72-HF-179-M2,,SIG,,SPA)+ 1358602900003 (72-HF-179(N,INL)72-HF-179-M2,,SIG,,RAB/SPA)) 1358602900004 Data for natural element divided by 180Hf abundance. 1358602900005 SAMPLE Elemental sample 1358602900006 DECAY-DATA (72-HF-179-M2,25.1D,DG,454.,0.686) 1358602900007 FACILITY (DYNAM,1USAANL) ANL fast neutron generator accelerator 1358602900008 INC-SOURCE (D-BE) 7-MeV deuterons on 0.15-cm-thick Be metal target1358602900009 INC-SPECT Neutron spectrum of <0.2 MeV to about 11.4 MeV. 1358602900010 METHOD Sample irradiated for about 110 hours. 1358602900011 Relative flux monitored by long counter. 1358602900012 CORRECTION Also corrected for 1358602900013 - decay of sample radioactivities during irradiation 1358602900014 period 1358602900015 ERR-ANALYS (ERR-T) absolute uncertainty. See table 6 in article 1358602900016 for contributions. 1358602900017 HISTORY (20090928A) Reaction corrected. 1358602900018 ENDBIB 16 0 1358602900019 COMMON 4 3 1358602900020 EN-MIN EN-MAX MONIT MONIT-ERR 1358602900021 MEV MEV MB MB 1358602900022 0.2 11.4 231. 14. 1358602900023 ENDCOMMON 3 0 1358602900024 DATA 2 1 1358602900025 DATA ERR-T 1358602900026 MB PER-CENT 1358602900027 3.08 9.9 1358602900028 ENDDATA 3 0 1358602900029 ENDSUBENT 28 0 1358602999999 ENDENTRY 29 0 1358699999999