ENTRY 12847 20160603 14181284700000001 SUBENT 12847001 20160603 14181284700100001 BIB 9 13 1284700100002 INSTITUTE (1USANBS) 1284700100003 REFERENCE (C,82ANTWER,,425,198209) 1284700100004 AUTHOR (G.P.Lamaze,E.D.Mcgarry,F.J.Schima) 1284700100005 TITLE Integral reaction rate measurements in 98-Cf-252 and 1284700100006 92-U-235 fission spectra. 1284700100007 FACILITY NBS 252-Cf irradiation facility and 1284700100008 NBS 235-U irradiation facility. 1284700100009 METHOD (ACTIV) 1284700100010 DETECTOR (GELI) Germanium-Lithium detector,60cm3 coaxial diode 1284700100011 resolution 0.8 keV at 122 keV and 1.77 keV at 1332keV. 1284700100012 STATUS (APRVD) G.P.Lamaze, 84/3/6. 1284700100013 HISTORY (19831104C) 1284700100014 (20160602A) OS. Corr.in sub.4. 1284700100015 ENDBIB 13 0 1284700100016 NOCOMMON 0 0 1284700100017 ENDSUBENT 16 0 1284700199999 SUBENT 12847002 20160603 14181284700200001 BIB 8 24 1284700200002 REACTION (26-FE-54(N,P)25-MN-54,,SIG,,FIS) 1284700200003 INC-SOURCE (CF252) Spont.fiss.Californium-252. Fission neutron 1284700200004 field source strength determined by a manganese sulfate1284700200005 bath technique in which the Cf source emission is 1284700200006 compared to that of NBS-I(a standard Ra-Be neutron 1284700200007 source). 1284700200008 SAMPLE Natural iron foils, 99.64% purity, 0.13 mm thick, 1284700200009 backed by 0.75 mm thick Ti foils 1284700200010 DECAY-DATA (25-MN-54,312.02D,DG,,0.9997) 1284700200011 CORRECTION Corrections are made for neutron scattering, the decay 1284700200012 of the 252-Cf, saturation of activity and attenuation. 1284700200013 Correction factor for scattering corrections = 1.006 1284700200014 ERR-ANALYS (ERR-T) Overall uncertainty, including uncertainties 1284700200015 due to 1284700200016 (ERR-1) source strength of NBS-I 1284700200017 (ERR-2) ratio of Cf to NBS-I 1284700200018 (ERR-3) source to foil distance 1284700200019 (ERR-4) efficiency 1284700200020 (ERR-5) scattering 1284700200021 (ERR-S) statistics 1284700200022 STATUS (PRELM) 1284700200023 (TABLE) Table 4 of reference 1284700200024 HISTORY (20160602A) Changed SF8 to FIS, replaced EN-MEAN by 1284700200025 KT=1.42 MeV, updated ERR-ANALYS, SAMPLE, CORRECTION 1284700200026 ENDBIB 24 0 1284700200027 COMMON 6 3 1284700200028 ERR-1 ERR-2 ERR-3 ERR-4 ERR-5 ERR-S 1284700200029 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 1284700200030 0.9 0.6 0.7 0.8 1.0 0.2 1284700200031 ENDCOMMON 3 0 1284700200032 DATA 3 1 1284700200033 KT DATA ERR-T 1284700200034 MEV MB MB 1284700200035 1.42 89. 2. 1284700200036 ENDDATA 3 0 1284700200037 ENDSUBENT 36 0 1284700299999 SUBENT 12847003 20160603 14181284700300001 BIB 8 23 1284700300002 REACTION (28-NI-58(N,P)27-CO-58,,SIG,,FIS) 1284700300003 INC-SOURCE (CF252) Spont.fiss.Californium-252. Fission neutron 1284700300004 field source strength determined by a manganese sulfate1284700300005 bath technique in which the Cf source emission is 1284700300006 compared to that of NBS-I(a standard Ra-Be neutron 1284700300007 source). 1284700300008 SAMPLE Two 0.25 mm thick natural Ni foils 1284700300009 DECAY-DATA (27-CO-58-G,70.78D,DG,,0.994) 1284700300010 CORRECTION Corrections are made for neutron scattering, the decay 1284700300011 of the 252-Cf, saturation of activity and attenuation. 1284700300012 Correction factor for scattering corrections = 1.004 1284700300013 ERR-ANALYS (ERR-T) Overall uncertainty, including uncertainties 1284700300014 due to 1284700300015 (ERR-1) source strength of NBS-I 1284700300016 (ERR-2) ratio of Cf to NBS-I 1284700300017 (ERR-3) source to foil distance 1284700300018 (ERR-4) efficiency 1284700300019 (ERR-5) scattering 1284700300020 (ERR-S) statistics 1284700300021 STATUS (PRELM) 1284700300022 (TABLE) Table 4 of reference 1284700300023 HISTORY (20160602A) Changed SF8 to FIS, replaced EN-MEAN by 1284700300024 KT=1.42 MeV, updated ERR-ANALYS, SAMPLE, CORRECTION 1284700300025 ENDBIB 23 0 1284700300026 COMMON 6 3 1284700300027 ERR-1 ERR-2 ERR-3 ERR-4 ERR-5 ERR-S 1284700300028 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 1284700300029 0.9 0.6 0.7 0.8 1.0 0.1 1284700300030 ENDCOMMON 3 0 1284700300031 DATA 3 1 1284700300032 KT DATA ERR-T 1284700300033 MEV MB MB 1284700300034 1.42 121. 2. 1284700300035 ENDDATA 3 0 1284700300036 ENDSUBENT 35 0 1284700399999 SUBENT 12847004 20160603 14181284700400001 BIB 8 23 1284700400002 REACTION (49-IN-115(N,INL)49-IN-115-M,,SIG,,FIS) 1284700400003 INC-SOURCE (CF252) Spont.fiss.Californium-252. Fission neutron 1284700400004 field source strength determined by a manganese sulfate1284700400005 bath technique in which the Cf source emission is 1284700400006 compared to that of NBS-I(a standard Ra-Be neutron 1284700400007 source). 1284700400008 SAMPLE Two pairs of 0.25 mm thick natural In foils 1284700400009 DECAY-DATA (49-IN-115-M,4.486HR,DG,,0.459) 1284700400010 CORRECTION Corrections are made for neutron scattering, the decay 1284700400011 of the 252-Cf, saturation of activity and attenuation. 1284700400012 Correction factor for scattering corrections = 1.01 1284700400013 ERR-ANALYS (ERR-T) Overall uncertainty, including uncertainties 1284700400014 due to 1284700400015 (ERR-1) source strength of NBS-I 1284700400016 (ERR-2) ratio of Cf to NBS-I 1284700400017 (ERR-3) source to foil distance 1284700400018 (ERR-4) efficiency 1284700400019 (ERR-5) scattering 1284700400020 (ERR-S) statistics 1284700400021 STATUS (TABLE) Table 4 of reference 1284700400022 HISTORY (20160602A) Changed SF8 to FIS, replaced EN-MEAN by 1284700400023 KT-DUMMY=1.42 MeV, updated ERR-ANALYS, SAMPLE, 1284700400024 CORRECTION 1284700400025 ENDBIB 23 0 1284700400026 COMMON 6 3 1284700400027 ERR-1 ERR-2 ERR-3 ERR-4 ERR-5 ERR-S 1284700400028 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 1284700400029 0.9 0.6 0.4 0.8 1.0 0.9 1284700400030 ENDCOMMON 3 0 1284700400031 DATA 3 1 1284700400032 KT-DUMMY DATA ERR-T 1284700400033 MEV MB MB 1284700400034 1.42 196. 4. 1284700400035 ENDDATA 3 0 1284700400036 ENDSUBENT 35 0 1284700499999 SUBENT 12847005 20160603 14181284700500001 BIB 9 19 1284700500002 REACTION (26-FE-54(N,P)25-MN-54,,SIG,,FIS) 1284700500003 INC-SOURCE 92-U-235 fission irradiation source located at the 1284700500004 center of nbs research reactor thermal column. 1284700500005 MONITOR (49-IN-115(N,INL)49-IN-115-M,,SIG,,FIS) 1284700500006 SAMPLE Two natural iron foils, 0.13 mm thick 1284700500007 DECAY-DATA (25-MN-54,312.02D,DG,,0.9997) 1284700500008 CORRECTION Correction is made to take into effect the difference 1284700500009 of the In-115(n,inl) sigma in the two fields. 1284700500010 In-115(n,inl)(252field)/In-115(n,inl)(235field)=1.05. 1284700500011 ERR-ANALYS (ERR-T) Overall uncertainty, including uncertainties 1284700500012 due to 1284700500013 (ERR-1) gamma counting efficiency 1284700500014 (ERR-2) flux gradient in cavity 1284700500015 (ERR-3) scattering correction in cavity 1284700500016 (ERR-4) uncertainty in fluence 1284700500017 (ERR-S) statistics 1284700500018 STATUS (PRELM) 1284700500019 (TABLE) Table 4 of reference 1284700500020 HISTORY (20160602A) Updated ERR-ANALYS, SAMPLE, CORRECTION 1284700500021 ENDBIB 19 0 1284700500022 COMMON 5 3 1284700500023 ERR-1 ERR-2 ERR-3 ERR-4 ERR-S 1284700500024 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 1284700500025 0.75 0.4 0.8 2.4 1.6 1284700500026 ENDCOMMON 3 0 1284700500027 DATA 3 1 1284700500028 EN-MEAN DATA ERR-T 1284700500029 MEV MB MB 1284700500030 1.98 79. 3. 1284700500031 ENDDATA 3 0 1284700500032 ENDSUBENT 31 0 1284700599999 SUBENT 12847006 20160603 14181284700600001 BIB 9 18 1284700600002 REACTION (28-NI-58(N,P)27-CO-58,,SIG,,FIS) 1284700600003 INC-SOURCE 92-U-235 fission irradiation source located at the 1284700600004 center of nbs research reactor thermal column. 1284700600005 MONITOR (49-IN-115(N,INL)49-IN-115-M,,SIG,,FIS) 1284700600006 SAMPLE Natural Ni foils, 0.25 and 0.09 mm thick 1284700600007 DECAY-DATA (27-CO-58-G,70.78D,DG,,0.994) 1284700600008 CORRECTION Correction is made to take into effect the difference 1284700600009 of the In-115(n,inl) sigma in the two fields. 1284700600010 In-115(n,inl)(252field)/In-115(n,inl)(235field)=1.05. 1284700600011 ERR-ANALYS (ERR-T) Overall uncertainty, including uncertainties 1284700600012 due to 1284700600013 (ERR-1) gamma counting efficiency 1284700600014 (ERR-2) flux gradient in cavity 1284700600015 (ERR-3) scattering correction in cavity 1284700600016 (ERR-4) uncertainty in fluence 1284700600017 (ERR-S) statistics 1284700600018 STATUS (TABLE) Table 4 of reference 1284700600019 HISTORY (20160602A) Updated ERR-ANALYS, SAMPLE, CORRECTION 1284700600020 ENDBIB 18 0 1284700600021 COMMON 5 3 1284700600022 ERR-1 ERR-2 ERR-3 ERR-4 ERR-S 1284700600023 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 1284700600024 0.75 0.4 0.8 2.4 0.17 1284700600025 ENDCOMMON 3 0 1284700600026 DATA 3 1 1284700600027 EN-MEAN DATA ERR-T 1284700600028 MEV MB MB 1284700600029 1.98 109. 3. 1284700600030 ENDDATA 3 0 1284700600031 ENDSUBENT 30 0 1284700699999 ENDENTRY 6 0 1284799999999