ENTRY 14354 20130122 13891435400000001 SUBENT 14354001 20130122 13891435400100001 BIB 13 28 1435400100002 TITLE Measurement of the Integral Capture and Fission Cross 1435400100003 Sections for 232Th in the CFRMF 1435400100004 AUTHOR (R.A.Anderl,Y.D.Harker) 1435400100005 INSTITUTE (1USAINL) 1435400100006 REFERENCE (C,79KNOX,,475,1979) 1435400100007 REL-REF (M,,R.C.Greenwood+,J,NTC,25,275,1977) 1435400100008 (M,,R.C.Greenwood+,P,NUREG/CP-0004(3),1207,1978) 1435400100009 FACILITY (REAC,1USAINL) Coupled Fast Reactivity Measurements 1435400100010 Facility (CFRMF). 1435400100011 INC-SOURCE (REAC) Neutron fluxes were 8.78E11 n/cm2sec and 1435400100012 8.73E11 n/cm2sec for irradiation 1 and 2, respectively.1435400100013 INC-SPECT CFRF neutron spectrum is similar to that in a fast 1435400100014 reactor. 1435400100015 DETECTOR (GELI) 65 cm3 closed-end coaxial detector. 1435400100016 PART-DET (G) 1435400100017 METHOD (ACTIV,GSPEC,INTB,STTA) Radiometric method when 1435400100018 saturation reaction rates (RR) are determined as RR = 1435400100019 (A D)/(b e N gamma delta), where A is the measured 1435400100020 peak area, b is the gamma-ray branching ratio, e is 1435400100021 detector efficiency, N number of atoms per isotope of 1435400100022 interest in the sample, gamma is the fission yield, D 1435400100023 is a decay/count factor and delta includes correction 1435400100024 factors. 1435400100025 ANALYSIS (PGS) Peak area determinations were made with 1435400100026 the GAUSS-V computer program. Peak efficiencies were 1435400100027 interpolated values based on the previously measured 1435400100028 efficiency curves. 1435400100029 HISTORY (20130122C) BP 1435400100030 ENDBIB 28 0 1435400100031 COMMON 1 3 1435400100032 EN-MEAN 1435400100033 MEV 1435400100034 0.72 1435400100035 ENDCOMMON 3 0 1435400100036 ENDSUBENT 35 0 1435400199999 SUBENT 14354002 20130122 13891435400200001 BIB 8 23 1435400200002 REACTION 1(79-AU-197(N,G)79-AU-198,,SGV,,FST/MSC) 1435400200003 Reaction rate in units reactions/sec-atom, 1435400200004 Irradiation 1 1435400200005 2(79-AU-197(N,G)79-AU-198,,SGV,,FST/MSC) 1435400200006 Reaction rate in units reactions/sec-atom, 1435400200007 Irradiation 2 1435400200008 METHOD 1Irradiation 1: Measured at 1435400200009 source to detector distance 25 cm for times between 1435400200010 2 and 21 days after end of irradiation 1435400200011 2Irradiation 2: Measured at 1435400200012 source to detector distance 25 and 10 cm for times 1435400200013 between 1 and 110 days after end of irradiation 1435400200014 SAMPLE Three 0.4 cm diameter, 0.0127 cm thick gold 1435400200015 foils. The data given are the average of the 3 1435400200016 reaction rates. 1435400200017 CORRECTION Not corrected for gamma-ray self absorption or 1435400200018 neutron resonance self-shielding. 1435400200019 STATUS (TABLE) Table II, page 477. 1435400200020 DECAY-DATA (79-AU-198,2.6956D,DG,411.794,0.9552) 1435400200021 ERR-ANALYS (ERR-T) The total error is dominated by branching 1435400200022 ratio and efficiency systematic errors. 1435400200023 COMMENT Reaction rates are given for 8.7x10**11 n/cm2 s reactor1435400200024 flux. 1435400200025 ENDBIB 23 0 1435400200026 NOCOMMON 0 0 1435400200027 DATA 4 1 1435400200028 DATA 1ERR-T 1DATA 2ERR-T 1435400200029 1/SEC PER-CENT 1/SEC PER-CENT 1435400200030 33.9E-14 1.9 33.74E-14 1.6 1435400200031 ENDDATA 3 0 1435400200032 ENDSUBENT 31 0 1435400299999 SUBENT 14354003 20130122 13891435400300001 BIB 8 35 1435400300002 REACTION 1(90-TH-232(N,G)90-TH-233,,SGV,,FST/MSC) 1435400300003 Reaction rate in units reactions/sec-atom, 1435400300004 Irradiation 1 1435400300005 2(90-TH-232(N,G)90-TH-233,,SGV,,FST/MSC) 1435400300006 Reaction rate in units reactions/sec-atom, 1435400300007 Irradiation 2 1435400300008 SAMPLE 1.27 cm diameter thorium metal foils with purity 1435400300009 99.96% (one - 161.6 mg, 0.01 cm thick; 1435400300010 two 22.2 mg, 0.00127 cm thick). 1435400300011 Each foil was wrapped in three 1435400300012 thicknesses of 0.00127 cm aluminum foil to minimize 1435400300013 the loss of fission gas. Each irradiation package 1435400300014 included three 0.4 cm diameter, 0.0127 cm thick gold 1435400300015 foils for monitoring reactor power level. 1435400300016 METHOD 1Irradiation 1: 161.6 mg Th foil. 6 spectra measured at 1435400300017 source to detector distance 25 cm for times between 1435400300018 2 and 21 days after end of irradiation 1435400300019 2Irradiation 2: 22.2 mg Th foil. 5 spectra measured at 1435400300020 source to detector distance 25 and 10 cm for times 1435400300021 between 1 and 110 days after end of irradiation 1435400300022 CORRECTION Correction factors were estimated 1435400300023 to account for gamma-ray self absorption in the 1435400300024 sample foils, for gamma-ray attenuation in the 1435400300025 aluminum cladding, for random summing/live timer 1435400300026 losses, for coincidence-summing losses, for 1435400300027 interferring gamma rays and for neutron resonance 1435400300028 self-shielding. 1435400300029 STATUS (TABLE) Table II, page 477. 1435400300030 DECAY-DATA (91-PA-233,26.96D,DG,311.9,0.386) 1435400300031 ERR-ANALYS (ERR-T) The total error is dominated by systematic 1435400300032 errors: 1435400300033 (ERR-1) branching ratio 1435400300034 (ERR-2) peak efficiency 1435400300035 COMMENT Reaction rates are given for 8.7x10**11 n/cm2 s reactor1435400300036 flux. 1435400300037 ENDBIB 35 0 1435400300038 COMMON 2 3 1435400300039 ERR-1 ERR-2 1435400300040 PER-CENT PER-CENT 1435400300041 1.3 1.5 1435400300042 ENDCOMMON 3 0 1435400300043 DATA 4 1 1435400300044 DATA 1ERR-T 1DATA 2ERR-T 2 1435400300045 1/SEC PER-CENT 1/SEC PER-CENT 1435400300046 25.64E-14 2.5 25.31E-14 2.2 1435400300047 ENDDATA 3 0 1435400300048 ENDSUBENT 47 0 1435400399999 SUBENT 14354004 20130122 13891435400400001 BIB 9 34 1435400400002 REACTION 1(90-TH-232(N,F),,SGV,,FST/MSC) in reactions/sec-atom 1435400400003 2(90-TH-232(N,F),,SGV,,FST/MSC) in reactions/sec-atom 1435400400004 3(90-TH-232(N,F),,SGV,,FST/MSC) in reactions/sec-atom 1435400400005 Weighted average of 1 and 2 (rounded) 1435400400006 METHOD Irradiation 1: 161.6 mg Th foil. 6 spectra measured at 1435400400007 source to detector distance 25 cm for times between 1435400400008 2 and 21 days after end of irradiation 1435400400009 SAMPLE 1.27 cm diameter thorium metal foils with purity 1435400400010 99.96% (one - 161.6 mg, 0.01 cm thick; 1435400400011 two 22.2 mg, 0.00127 cm thick). 1435400400012 Each foil was wrapped in three 1435400400013 thicknesses of 0.00127 cm aluminum foil to minimize 1435400400014 the loss of fission gas. Each irradiation package 1435400400015 included three 0.4 cm diameter, 0.0127 cm thick gold 1435400400016 foils for monitoring reactor power level. 1435400400017 CORRECTION Correction factors were estimated 1435400400018 to account for gamma-ray self absorption in the 1435400400019 sample foils, for gamma-ray attenuation in the 1435400400020 aluminum cladding, for random summing/live timer 1435400400021 losses, for coincidence-summing losses, for 1435400400022 interferring gamma rays and for neutron resonance 1435400400023 self-shielding. 1435400400024 STATUS (TABLE) Table II, page 477. 1435400400025 DECAY-DATA1(56-BA-140,12.789D,DG,537.35,0.244) 1435400400026 2(57-LA-140,40.26HR,DG,1596.18,0.9540) 1435400400027 ERR-ANALYS (ERR-T) The total error is dominated by systematic 1435400400028 errors: 1435400400029 (ERR-1) fission yield 1435400400030 (ERR-2) peak efficiency 1435400400031 COMMENT Reaction rates are given for 8.7x10**11 n/cm2 s 1435400400032 reactor flux. 1435400400033 ASSUMED Fission yields from M. E. Meek and B. F. Rider, 1435400400034 "Compilation of fission Product Yields, Vallecitos 1435400400035 Nuclear Center", NEDO-12154-2 (January 1977). 1435400400036 ENDBIB 34 0 1435400400037 COMMON 2 3 1435400400038 ERR-1 ERR-2 1435400400039 PER-CENT PER-CENT 1435400400040 4.0 1.5 1435400400041 ENDCOMMON 3 0 1435400400042 DATA 6 1 1435400400043 DATA 1ERR-T 1DATA 2ERR-T 2DATA 3ERR-T 31435400400044 1/SEC PER-CENT 1/SEC PER-CENT 1/SEC PER-CENT 1435400400045 1.716E-14 4.5 1.715E-14 4.3 1.72E-14 4.21435400400046 ENDDATA 3 0 1435400400047 ENDSUBENT 46 0 1435400499999 SUBENT 14354005 20130122 13891435400500001 BIB 9 34 1435400500002 REACTION 1(90-TH-232(N,F),,SGV,,FST/MSC) in reactions/sec-atom 1435400500003 2(90-TH-232(N,F),,SGV,,FST/MSC) in reactions/sec-atom 1435400500004 3(90-TH-232(N,F),,SGV,,FST/MSC) in reactions/sec-atom 1435400500005 Weighted average of 1 and 2 (rounded) 1435400500006 METHOD Irradiation 2: 22.2 mg Th foil. 5 spectra measured at 1435400500007 source to detector distance 25 and 10 cm for times 1435400500008 between 1 and 110 days after end of irradiation 1435400500009 SAMPLE 1.27 cm diameter thorium metal foils with purity 1435400500010 99.96% (one - 161.6 mg, 0.01 cm thick; 1435400500011 two 22.2 mg, 0.00127 cm thick). 1435400500012 Each foil was wrapped in three 1435400500013 thicknesses of 0.00127 cm aluminum foil to minimize 1435400500014 the loss of fission gas. Each irradiation package 1435400500015 included three 0.4 cm diameter, 0.0127 cm thick gold 1435400500016 foils for monitoring reactor power level. 1435400500017 CORRECTION Correction factors were estimated 1435400500018 to account for gamma-ray self absorption in the 1435400500019 sample foils, for gamma-ray attenuation in the 1435400500020 aluminum cladding, for random summing/live timer 1435400500021 losses, for coincidence-summing losses, for 1435400500022 interferring gamma rays and for neutron resonance 1435400500023 self-shielding. 1435400500024 STATUS (TABLE) Table II, page 477. 1435400500025 DECAY-DATA1(56-BA-140,12.789D,DG,537.35,0.244) 1435400500026 2(57-LA-140,40.26HR,DG,1596.18,0.9540) 1435400500027 ERR-ANALYS (ERR-T) The total error is dominated by systematic 1435400500028 errors: 1435400500029 (ERR-1) fission yield 1435400500030 (ERR-2) peak efficiency 1435400500031 COMMENT Reaction rates are given for 8.7x10**11 n/cm2 s 1435400500032 reactor flux. 1435400500033 ASSUMED Fission yields from M. E. Meek and B. F. Rider, 1435400500034 "Compilation of fission Product Yields, Vallecitos 1435400500035 Nuclear Center", NEDO-12154-2 (January 1977). 1435400500036 ENDBIB 34 0 1435400500037 COMMON 2 3 1435400500038 ERR-1 ERR-2 1435400500039 PER-CENT PER-CENT 1435400500040 4.0 1.5 1435400500041 ENDCOMMON 3 0 1435400500042 DATA 6 1 1435400500043 DATA 1ERR-T 1DATA 2ERR-T 2DATA 3ERR-T 31435400500044 1/SEC PER-CENT 1/SEC PER-CENT 1/SEC PER-CENT 1435400500045 1.727E-14 4.7 1.706E-14 4.5 1.71E-14 4.31435400500046 ENDDATA 3 0 1435400500047 ENDSUBENT 46 0 1435400599999 SUBENT 14354006 20130122 13891435400600001 BIB 4 11 1435400600002 REACTION (90-TH-232(N,G)90-TH-233,,SIG,,FST) 1435400600003 STATUS (TABLE) Page 477. 1435400600004 (DEP,14354003) These data are an average of 1435400600005 two irradiation measurements. 1435400600006 ANALYSIS Cross sections were obtained by dividing the capture 1435400600007 reaction rates by the corresponding neutron fluxes. 1435400600008 ERR-ANALYS (ERR-T) The total error is dominated by systematic 1435400600009 errors: 1435400600010 (ERR-1) branching ratio 1435400600011 (ERR-2) peak efficiency 1435400600012 (ERR-3) fission chamber flux uncertainty 1435400600013 ENDBIB 11 0 1435400600014 COMMON 3 3 1435400600015 ERR-1 ERR-2 ERR-3 1435400600016 PER-CENT PER-CENT PER-CENT 1435400600017 1.3 1.5 1.9 1435400600018 ENDCOMMON 3 0 1435400600019 DATA 2 1 1435400600020 DATA ERR-T 1435400600021 MB PER-CENT 1435400600022 291.0 3.1 1435400600023 ENDDATA 3 0 1435400600024 ENDSUBENT 23 0 1435400699999 SUBENT 14354007 20130122 13891435400700001 BIB 4 11 1435400700002 REACTION (90-TH-232(N,F),,SIG,,FST) 1435400700003 STATUS (TABLE) Page 478. 1435400700004 (DEP,14354004) 1435400700005 (DEP,14354005) These data are an average of 1435400700006 two irradiation measurements. 1435400700007 ANALYSIS Cross sections were obtained by dividing the fission 1435400700008 reaction rates by the corresponding neutron fluxes. 1435400700009 ERR-ANALYS (ERR-T) The total error is dominated by systematic 1435400700010 errors: 1435400700011 (ERR-1) fission yield 1435400700012 (ERR-2) fission chamber flux uncertainty 1435400700013 ENDBIB 11 0 1435400700014 COMMON 2 3 1435400700015 ERR-1 ERR-2 1435400700016 PER-CENT PER-CENT 1435400700017 4.0 1.9 1435400700018 ENDCOMMON 3 0 1435400700019 DATA 2 1 1435400700020 DATA ERR-T 1435400700021 MB PER-CENT 1435400700022 19.6 4.7 1435400700023 ENDDATA 3 0 1435400700024 ENDSUBENT 23 0 1435400799999 ENDENTRY 7 0 1435499999999