ENTRY 14171 20171020 14351417100000001 SUBENT 14171001 20171020 14351417100100001 BIB 8 13 1417100100002 TITLE Reaction rate measurements and integral cross 1417100100003 sections using the nbs 252Cf fission neutron indoor 1417100100004 irradiation facility 1417100100005 AUTHOR (V.Spiegel,C.M.Eisenhauer,J.A.Grundl,G.C.Martin Jr) 1417100100006 REFERENCE (S,NUREG/CP-0004,(3),959,1979) 1417100100007 (C,77PALOALTO,2,959,1977) Preliminary data. 1417100100008 INSTITUTE (1USANBS,1USAGEP) 1417100100009 FACILITY (CRASS,1USANBS) Nbs 252Cf standard fission spectrum 1417100100010 indoor facility. 1417100100011 INC-SPECT Cf-252 fission neutron spectrum. 1417100100012 DETECTOR (GE,NAICR) 1417100100013 HISTORY (20160927C) BP 1417100100014 (20171020A) BP: Added preliminary data reference. 1417100100015 ENDBIB 13 0 1417100100016 COMMON 1 3 1417100100017 KT-DUMMY 1417100100018 MEV 1417100100019 1.42 1417100100020 ENDCOMMON 3 0 1417100100021 ENDSUBENT 20 0 1417100199999 SUBENT 14171002 20160927 14241417100200001 BIB 6 18 1417100200002 REACTION (28-NI-58(N,P)27-CO-58,,SIG,,FIS) 1417100200003 METHOD (ACTIV,INTB) Dosimeter packet III. 252Cf fission 1417100200004 neutron source. 1417100200005 ERR-ANALYS (ERR-T) rms sum, all uncertainties are 2 sigma. 1417100200006 (ERR-S) Counting statistics. 1417100200007 (ERR-1) Dosimeter weight. 1417100200008 (ERR-2) Detection efficiency. 1417100200009 (ERR-3) Source positioning. 1417100200010 (ERR-4) Peak count determination. 1417100200011 (ERR-5) Peak background/Compton subtraction. 1417100200012 (ERR-6) Dosimeter gamma attenuation,decay during count.1417100200013 (ERR-7) Half-life correction. 1417100200014 (ERR-8) Gammas per decay. 1417100200015 CORRECTION Applied correction: 1.012. Neutron Scattering 1417100200016 Correction explained on p.962. 1417100200017 DECAY-DATA (27-CO-58-G,70.78D,DG,810.8,0.9945, 1417100200018 DG,810.0,1.00) 1417100200019 STATUS (TABLE) table 2, page 963. 1417100200020 ENDBIB 18 0 1417100200021 COMMON 9 6 1417100200022 ERR-S ERR-1 ERR-2 ERR-3 ERR-4 ERR-5 1417100200023 ERR-6 ERR-7 ERR-8 1417100200024 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 1417100200025 PER-CENT PER-CENT PER-CENT 1417100200026 1.0 0.03 2.2 0.3 1.0 1.01417100200027 0.2 0.1 0.05 1417100200028 ENDCOMMON 6 0 1417100200029 DATA 2 1 1417100200030 DATA ERR-T 1417100200031 MB PER-CENT 1417100200032 118.8 4.6 1417100200033 ENDDATA 3 0 1417100200034 ENDSUBENT 33 0 1417100299999 SUBENT 14171003 20160927 14241417100300001 BIB 6 17 1417100300002 REACTION (13-AL-27(N,A)11-NA-24,,SIG,,FIS) 1417100300003 METHOD (ACTIV,INTB) Dosimeter packet I. 252Cf fission 1417100300004 neutron source. 1417100300005 ERR-ANALYS (ERR-T) rms sum, all uncertainties are 2 sigma. 1417100300006 (ERR-S) Counting statistics. 1417100300007 (ERR-1) Dosimeter weight. 1417100300008 (ERR-2) Detection efficiency. 1417100300009 (ERR-3) Source positioning. 1417100300010 (ERR-4) Peak count determination. 1417100300011 (ERR-5) Peak background/Compton subtraction. 1417100300012 (ERR-6) Dosimeter gamma attenuation,decay during count.1417100300013 (ERR-7) Half-life correction. 1417100300014 (ERR-8) Gammas per decay. 1417100300015 CORRECTION Applied correction: 0.963. Neutron Scattering 1417100300016 Correction explained on p.962. 1417100300017 DECAY-DATA (11-NA-24,15.00HR,DG,2754.1,0.9986) 1417100300018 STATUS (TABLE) table 2, page 963. 1417100300019 ENDBIB 17 0 1417100300020 COMMON 9 6 1417100300021 ERR-S ERR-1 ERR-2 ERR-3 ERR-4 ERR-5 1417100300022 ERR-6 ERR-7 ERR-8 1417100300023 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 1417100300024 PER-CENT PER-CENT PER-CENT 1417100300025 2.0 0.03 5.0 0.6 1.5 2.01417100300026 1.0 1.0 0.01 1417100300027 ENDCOMMON 6 0 1417100300028 DATA 2 1 1417100300029 DATA ERR-T 1417100300030 MB PER-CENT 1417100300031 1.06 7.3 1417100300032 ENDDATA 3 0 1417100300033 ENDSUBENT 32 0 1417100399999 SUBENT 14171004 20160927 14241417100400001 BIB 6 17 1417100400002 REACTION (13-AL-27(N,A)11-NA-24,,SIG,,FIS) 1417100400003 METHOD (ACTIV,INTB) Dosimeter packet II. 252Cf fission 1417100400004 neutron source. 1417100400005 ERR-ANALYS (ERR-T) rms sum, all uncertainties are 2 sigma. 1417100400006 (ERR-S) Counting statistics. 1417100400007 (ERR-1) Dosimeter weight. 1417100400008 (ERR-2) Detection efficiency. 1417100400009 (ERR-3) Source positioning. 1417100400010 (ERR-4) Peak count determination. 1417100400011 (ERR-5) Peak background/Compton subtraction. 1417100400012 (ERR-6) Dosimeter gamma attenuation,decay during count.1417100400013 (ERR-7) Half-life correction. 1417100400014 (ERR-8) Gammas per decay. 1417100400015 CORRECTION Applied correction: 0.992. Neutron Scattering 1417100400016 Correction explained on p.962. 1417100400017 DECAY-DATA (11-NA-24,15.00HR,DG,2754.1,0.9986) 1417100400018 STATUS (TABLE) table 2, page 963. 1417100400019 ENDBIB 17 0 1417100400020 COMMON 9 6 1417100400021 ERR-S ERR-1 ERR-2 ERR-3 ERR-4 ERR-5 1417100400022 ERR-6 ERR-7 ERR-8 1417100400023 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 1417100400024 PER-CENT PER-CENT PER-CENT 1417100400025 2.0 0.03 5.0 0.6 1.5 2.01417100400026 1.0 1.0 0.01 1417100400027 ENDCOMMON 6 0 1417100400028 DATA 2 1 1417100400029 DATA ERR-T 1417100400030 MB PER-CENT 1417100400031 1.06 7.1 1417100400032 ENDDATA 3 0 1417100400033 ENDSUBENT 32 0 1417100499999 SUBENT 14171005 20160927 14241417100500001 BIB 6 17 1417100500002 REACTION (22-TI-46(N,P)21-SC-46,,SIG,,FIS) 1417100500003 METHOD (ACTIV,INTB) Dosimeter packet I. 252Cf fission 1417100500004 neutron source. 1417100500005 ERR-ANALYS (ERR-T) rms sum, all uncertainties are 2 sigma. 1417100500006 (ERR-S) Counting statistics. 1417100500007 (ERR-1) Dosimeter weight. 1417100500008 (ERR-2) Detection efficiency. 1417100500009 (ERR-3) Source positioning. 1417100500010 (ERR-4) Peak count determination. 1417100500011 (ERR-5) Peak background/Compton subtraction. 1417100500012 (ERR-6) Dosimeter gamma attenuation,decay during count.1417100500013 (ERR-7) Half-life correction. 1417100500014 (ERR-8) Gammas per decay. 1417100500015 CORRECTION Applied correction: 0.989. Neutron Scattering 1417100500016 Correction explained on p.962. 1417100500017 DECAY-DATA (21-SC-46-G,83.85D,DG,1120.5,0.9999) 1417100500018 STATUS (TABLE) table 2, page 963. 1417100500019 ENDBIB 17 0 1417100500020 COMMON 9 6 1417100500021 ERR-S ERR-1 ERR-2 ERR-3 ERR-4 ERR-5 1417100500022 ERR-6 ERR-7 ERR-8 1417100500023 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 1417100500024 PER-CENT PER-CENT PER-CENT 1417100500025 1.5 0.03 4.5 0.6 1.2 1.21417100500026 0.4 0.3 0.1 1417100500027 ENDCOMMON 6 0 1417100500028 DATA 2 1 1417100500029 DATA ERR-T 1417100500030 MB PER-CENT 1417100500031 15.0 6.5 1417100500032 ENDDATA 3 0 1417100500033 ENDSUBENT 32 0 1417100599999 SUBENT 14171006 20160927 14241417100600001 BIB 6 17 1417100600002 REACTION (22-TI-47(N,P)21-SC-47,,SIG,,FIS) 1417100600003 METHOD (ACTIV,INTB) Dosimeter packet I. 252Cf fission 1417100600004 neutron source. 1417100600005 ERR-ANALYS (ERR-T) rms sum, all uncertainties are 2 sigma. 1417100600006 (ERR-S) Counting statistics. 1417100600007 (ERR-1) Dosimeter weight. 1417100600008 (ERR-2) Detection efficiency. 1417100600009 (ERR-3) Source positioning. 1417100600010 (ERR-4) Peak count determination. 1417100600011 (ERR-5) Peak background/Compton subtraction. 1417100600012 (ERR-6) Dosimeter gamma attenuation,decay during count.1417100600013 (ERR-7) Half-life correction. 1417100600014 (ERR-8) Gammas per decay. 1417100600015 CORRECTION Applied correction: 0.989. Neutron Scattering 1417100600016 Correction explained on p.962. 1417100600017 DECAY-DATA (21-SC-47,3.422D,DG,159.4,0.68) 1417100600018 STATUS (TABLE) table 2, page 963. 1417100600019 ENDBIB 17 0 1417100600020 COMMON 9 6 1417100600021 ERR-S ERR-1 ERR-2 ERR-3 ERR-4 ERR-5 1417100600022 ERR-6 ERR-7 ERR-8 1417100600023 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 1417100600024 PER-CENT PER-CENT PER-CENT 1417100600025 1.0 0.03 3.5 0.4 1.5 1.21417100600026 0.6 0.1 2.0 1417100600027 ENDCOMMON 6 0 1417100600028 DATA 2 1 1417100600029 DATA ERR-T 1417100600030 MB PER-CENT 1417100600031 20.2 6.2 1417100600032 ENDDATA 3 0 1417100600033 ENDSUBENT 32 0 1417100699999 SUBENT 14171007 20160927 14241417100700001 BIB 6 17 1417100700002 REACTION (22-TI-48(N,P)21-SC-48,,SIG,,FIS) 1417100700003 METHOD (ACTIV,INTB) Dosimeter packet I. 252Cf fission 1417100700004 neutron source. 1417100700005 ERR-ANALYS (ERR-T) rms sum, all uncertainties are 2 sigma. 1417100700006 (ERR-S) Counting statistics. 1417100700007 (ERR-1) Dosimeter weight. 1417100700008 (ERR-2) Detection efficiency. 1417100700009 (ERR-3) Source positioning. 1417100700010 (ERR-4) Peak count determination. 1417100700011 (ERR-5) Peak background/Compton subtraction. 1417100700012 (ERR-6) Dosimeter gamma attenuation,decay during count.1417100700013 (ERR-7) Half-life correction. 1417100700014 (ERR-8) Gammas per decay. 1417100700015 CORRECTION Applied correction: 0.989. Neutron Scattering 1417100700016 Correction explained on p.962. 1417100700017 DECAY-DATA (21-SC-48,1.83D,DG,1312.0,0.9999) 1417100700018 STATUS (TABLE) table 2, page 963. 1417100700019 ENDBIB 17 0 1417100700020 COMMON 9 6 1417100700021 ERR-S ERR-1 ERR-2 ERR-3 ERR-4 ERR-5 1417100700022 ERR-6 ERR-7 ERR-8 1417100700023 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 1417100700024 PER-CENT PER-CENT PER-CENT 1417100700025 2.0 0.03 6.5 0.6 1.2 1.51417100700026 1.0 0.8 0.1 1417100700027 ENDCOMMON 6 0 1417100700028 DATA 2 1 1417100700029 DATA ERR-T 1417100700030 MB PER-CENT 1417100700031 0.434 8.3 1417100700032 ENDDATA 3 0 1417100700033 ENDSUBENT 32 0 1417100799999 SUBENT 14171008 20160927 14241417100800001 BIB 6 17 1417100800002 REACTION (26-FE-54(N,P)25-MN-54,,SIG,,FIS) 1417100800003 METHOD (ACTIV,INTB) Dosimeter packet II. 252Cf fission 1417100800004 neutron source. 1417100800005 ERR-ANALYS (ERR-T) rms sum, all uncertainties are 2 sigma. 1417100800006 (ERR-S) Counting statistics. 1417100800007 (ERR-1) Dosimeter weight. 1417100800008 (ERR-2) Detection efficiency. 1417100800009 (ERR-3) Source positioning. 1417100800010 (ERR-4) Peak count determination. 1417100800011 (ERR-5) Peak background/Compton subtraction. 1417100800012 (ERR-6) Dosimeter gamma attenuation,decay during count.1417100800013 (ERR-7) Half-life correction. 1417100800014 (ERR-8) Gammas per decay. 1417100800015 CORRECTION Applied correction: 0.987. Neutron Scattering 1417100800016 Correction explained on p.962. 1417100800017 DECAY-DATA (25-MN-54,312.5D,DG,834.8,0.9998) 1417100800018 STATUS (TABLE) table 2, page 963. 1417100800019 ENDBIB 17 0 1417100800020 COMMON 9 6 1417100800021 ERR-S ERR-1 ERR-2 ERR-3 ERR-4 ERR-5 1417100800022 ERR-6 ERR-7 ERR-8 1417100800023 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 1417100800024 PER-CENT PER-CENT PER-CENT 1417100800025 1.2 0.03 3.5 0.3 1.2 2.01417100800026 0.4 0.01 0.01 1417100800027 ENDCOMMON 6 0 1417100800028 DATA 2 1 1417100800029 DATA ERR-T 1417100800030 MB PER-CENT 1417100800031 90.0 5.7 1417100800032 ENDDATA 3 0 1417100800033 ENDSUBENT 32 0 1417100899999 SUBENT 14171009 20160927 14241417100900001 BIB 6 20 1417100900002 REACTION (92-U-238(N,F)56-BA-140,,SIG,,FIS) 1417100900003 METHOD (ACTIV,INTB) Dosimeter packet IV. 252Cf fission 1417100900004 neutron source. 1417100900005 ERR-ANALYS (ERR-T) rms sum, all uncertainties are 2 sigma. 1417100900006 (ERR-S) Counting statistics. 1417100900007 (ERR-1) Dosimeter weight. 1417100900008 (ERR-2) Detection efficiency. 1417100900009 (ERR-3) Source positioning. 1417100900010 (ERR-4) Peak count determination. 1417100900011 (ERR-5) Peak background/Compton subtraction. 1417100900012 (ERR-6) Dosimeter gamma attenuation,decay during count.1417100900013 (ERR-7) Half-life correction. 1417100900014 (ERR-8) Gammas per decay. 1417100900015 (ERR-9) La/Ba conversion. 1417100900016 (ERR-10) Fission yield. 1417100900017 CORRECTION Applied correction: 1.025. Neutron Scattering 1417100900018 Correction explained on p.962. 1417100900019 DECAY-DATA (56-BA-140,12.79D) 1417100900020 (57-LA-140,40.26HR,DG,1596.2,0.9533) 1417100900021 STATUS (TABLE) table 2, page 963. 1417100900022 ENDBIB 20 0 1417100900023 COMMON 11 6 1417100900024 ERR-S ERR-1 ERR-2 ERR-3 ERR-4 ERR-5 1417100900025 ERR-6 ERR-7 ERR-8 ERR-9 ERR-10 1417100900026 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 1417100900027 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 1417100900028 2.1 0.5 6.0 1.0 1.3 5.01417100900029 1.0 0.05 0.3 0.6 1.5 1417100900030 ENDCOMMON 6 0 1417100900031 DATA 2 1 1417100900032 DATA ERR-T 1417100900033 MB PER-CENT 1417100900034 284.0 9.6 1417100900035 ENDDATA 3 0 1417100900036 ENDSUBENT 35 0 1417100999999 SUBENT 14171010 20160927 14241417101000001 BIB 6 21 1417101000002 REACTION (93-NP-237(N,F)56-BA-140,,SIG,,FIS) 1417101000003 METHOD (ACTIV,INTB) Dosimeter packet IV. 252Cf fission 1417101000004 neutron source. 1417101000005 ERR-ANALYS (ERR-T) rms sum, all uncertainties are 2 sigma. 1417101000006 (ERR-S) Counting statistics. 1417101000007 (ERR-1) Dosimeter weight. 1417101000008 (ERR-2) Detection efficiency. 1417101000009 (ERR-3) Source positioning. 1417101000010 (ERR-4) Peak count determination. 1417101000011 (ERR-5) Peak background/Compton subtraction. 1417101000012 (ERR-6) Dosimeter gamma attenuation,decay during count.1417101000013 (ERR-7) Half-life correction. 1417101000014 (ERR-8) Gammas per decay. 1417101000015 (ERR-9) La/Ba conversion. 1417101000016 (ERR-10) Fission yield. 1417101000017 (ERR-11) 238U contribution. 1417101000018 CORRECTION Applied correction: 1.034. Neutron Scattering 1417101000019 Correction explained on p.962. 1417101000020 DECAY-DATA (56-BA-140,12.79D) 1417101000021 (57-LA-140,40.26HR,DG,1596.2,0.9533) 1417101000022 STATUS (TABLE) table 2, page 963. 1417101000023 ENDBIB 21 0 1417101000024 COMMON 12 6 1417101000025 ERR-S ERR-1 ERR-2 ERR-3 ERR-4 ERR-5 1417101000026 ERR-6 ERR-7 ERR-8 ERR-9 ERR-10 ERR-11 1417101000027 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 1417101000028 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 1417101000029 2.4 1.0 6.0 1.0 1.6 5.01417101000030 0.5 0.05 0.3 0.6 1.5 0.51417101000031 ENDCOMMON 6 0 1417101000032 DATA 2 1 1417101000033 DATA ERR-T 1417101000034 MB PER-CENT 1417101000035 1180.0 11.5 1417101000036 ENDDATA 3 0 1417101000037 ENDSUBENT 36 0 1417101099999 SUBENT 14171011 20160927 14241417101100001 BIB 6 20 1417101100002 REACTION (92-U-235(N,F)56-BA-140,,SIG,,FIS) 1417101100003 METHOD (ACTIV,INTB) Dosimeter packet IV. 252Cf fission 1417101100004 neutron source. 1417101100005 ERR-ANALYS (ERR-T) rms sum, all uncertainties are 2 sigma. 1417101100006 (ERR-S) Counting statistics. 1417101100007 (ERR-1) Dosimeter weight. 1417101100008 (ERR-2) Detection efficiency. 1417101100009 (ERR-3) Source positioning. 1417101100010 (ERR-4) Peak count determination. 1417101100011 (ERR-5) Peak background/Compton subtraction. 1417101100012 (ERR-6) Dosimeter gamma attenuation,decay during count.1417101100013 (ERR-7) Half-life correction. 1417101100014 (ERR-8) Gammas per decay. 1417101100015 (ERR-9) La/Ba conversion. 1417101100016 (ERR-10) Fission yield. 1417101100017 CORRECTION Applied correction: 1.036. Neutron Scattering 1417101100018 Correction explained on p.962. 1417101100019 DECAY-DATA (56-BA-140,12.79D) 1417101100020 (57-LA-140,40.26HR,DG,1596.2,0.9533) 1417101100021 STATUS (TABLE) table 2, page 963. 1417101100022 ENDBIB 20 0 1417101100023 COMMON 11 6 1417101100024 ERR-S ERR-1 ERR-2 ERR-3 ERR-4 ERR-5 1417101100025 ERR-6 ERR-7 ERR-8 ERR-9 ERR-10 1417101100026 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 1417101100027 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 1417101100028 3.9 1.5 7.0 1.0 2.0 5.51417101100029 0.5 0.05 0.3 0.6 3.0 1417101100030 ENDCOMMON 6 0 1417101100031 DATA 2 1 1417101100032 DATA ERR-T 1417101100033 MB PER-CENT 1417101100034 1140.0 9.7 1417101100035 ENDDATA 3 0 1417101100036 ENDSUBENT 35 0 1417101199999 ENDENTRY 11 0 1417199999999