ENTRY 23617 20250219 23212361700000001 SUBENT 23617001 20250219 23212361700100001 BIB 17 66 2361700100002 TITLE Measurements of neutron capture cross-sections for 2361700100003 nuclides of interest in decommissioning: 45Sc, 63Cu, 2361700100004 64Zn, 109Ag, and 113In 2361700100005 AUTHOR (S.Nakamura,Y.Shibahara,S.Endo,G.Rovira,A.Kimura) 2361700100006 INSTITUTE (2JPNJAE,2JPNKTO) 2361700100007 REFERENCE (J,NST,61,1415,2024) 2361700100008 #doi:10.1080/00223131.2024.2346347 2361700100009 FACILITY (REAC,2JPNKTO) 2361700100010 Kyoto University Research Reactor (KUR) . 2361700100011 INC-SOURCE (REAC)The graphite thermal column (TC-Pn) in KUR. 2361700100012 The nominal neutron flux intensity of TC-Pn is 2361700100013 5.86E+10 (n/cm2/sec) at 1 MW power operation. 2361700100014 The AUTHORs confirmed that the higher part of the TC-Pn2361700100015 was well thermalized on the basis of Westcott 2361700100016 convention using neutron flux monitors: Au-197, Co-59, 2361700100017 and Mo-98. (See Fig. 5 in the REFERENCE.) 2361700100018 METHOD (ACTIV,GSPEC) Based on Westcott convention method. 2361700100019 Because the neutron flux in the TC-Pn is well 2361700100020 thermalized, epithermal component in Westcott 2361700100021 convention method was negligibly small. 2361700100022 DETECTOR (HPGE) High purity germanium detector, relative 2361700100023 efficiency of 25%. 2361700100024 The gamma-ray peak efficiencies of the Ge detector 2361700100025 were measured using a Eu-152 source and a mixed source 2361700100026 AM-8140 (Am-241, Cd-109, Co-57, Ce-139, Hg-203, Sn-113,2361700100027 Cs-137, Co-60 and Y-88) . 2361700100028 The uncertainty in the source radioactivity was 1.5% 2361700100029 for both of the standard sources. 2361700100030 ANALYSIS The reaction rates of the target reactions were 2361700100031 obtained from the yields of the gamma rays emitted 2361700100032 from the irradiated samples. 2361700100033 The thermal-neutron fluxes were derived using the 2361700100034 reaction rates and the thermal cross section of the 2361700100035 monitors. 2361700100036 - For Sc-45, Cu-63, Ag-109 and In-113: 2361700100037 (5.904+-0.102)E+10 (n/cm2/sec) 2361700100038 - For Zn-64 and 68: (6.205+-0.107)E+10 (n/cm2/sec) 2361700100039 The capture cross sections were derived using the 2361700100040 reaction rates and the thermal-neutron fluxes. 2361700100041 The thermal capture cross sections for monitors and 2361700100042 the g-factors were taken from the REL-REF. 2361700100043 For Mo-98, the thermal capture cross section was taken 2361700100044 from an AUTHOR's unpublished previous measurement. 2361700100045 CORRECTION Self-shielding coefficients for thermal neutrons were 2361700100046 calculated from neutron capture cross-sections and 2361700100047 area densities of the sample and the monitors. 2361700100048 The coincidence summing effect was estimated from the 2361700100049 peak-to-total ratios and the peak efficiencies. 2361700100050 DECAY-DATA (79-AU-198-G,2.6943D,DG,411.80,0.9562) 2361700100051 (27-CO-60-G,5.2711YR,DG,1173.24,0.9985, 2361700100052 DG,1332.49,0.99826) 2361700100053 (42-MO-99,2.7479D,DG,739.50,0.1212) 2361700100054 ASSUMED Thermal capture cross sections of the monitors were 2361700100055 assumed to be well known to determine the thermal 2361700100056 neutron flux. 2361700100057 (ASSUM1,79-AU-197(N,G)79-AU-198,,SIG) 2361700100058 (ASSUM2,27-CO-59(N,G)27-CO-60,,SIG) 2361700100059 (ASSUM3,42-MO-98(N,G)42-MO-99,,SIG) 2361700100060 ERR-ANALYS (ASSUM1-ERR) Uncertainty of Au-197 thermal C.S. 2361700100061 (ASSUM2-ERR) Uncertainty of Co-59 thermal C.S. 2361700100062 (ASSUM3-ERR) Uncertainty of Mo-98 thermal C.S. 2361700100063 REL-REF (R,,S.F.Mughabghab,B,NEUT.RES,,,2018) 2361700100064 COMMENT AUTHOR's assumed cross section of Mo-98 0.132+-0.006 b 2361700100065 is close to that given in REL-REF (0.130+-0.06 b) . 2361700100066 STATUS (APRVD) Proofread by Shoji Nakamura (2025-02-19) 2361700100067 HISTORY (20250219C) By A.Kimura. 2361700100068 ENDBIB 66 0 2361700100069 COMMON 6 3 2361700100070 ASSUM1 ASSUM1-ERR ASSUM2 ASSUM2-ERR ASSUM3 ASSUM3-ERR 2361700100071 B B B B B B 2361700100072 98.65 0.09 37.18 0.06 0.132 0.0062361700100073 ENDCOMMON 3 0 2361700100074 ENDSUBENT 73 0 2361700199999 SUBENT 23617002 20250219 23212361700200001 BIB 5 24 2361700200002 REACTION (21-SC-45(N,G)21-SC-46,,SIG) 2361700200003 SAMPLE Sample: Sc-nat metal foil 1.080+-0.001 mg 2361700200004 Monitor: Co-nat metal foil 0.631+-0.001 mg 2361700200005 Mo-nat metal foil 8.351+-0.001 mg 2361700200006 Au/Al Alloy wire 4.441+-0.001 mg 2361700200007 DECAY-DATA (21-SC-46-G,83.787D,DG,889.28,0.9998374, 2361700200008 DG,1120.55,0.9997) 2361700200009 ERR-ANALYS (ERR-T) Total uncertainty. 2361700200010 (ERR-S) Statistical uncertainty. 2361700200011 (1.5977+-0.0083)E-12 (event/s) 2361700200012 (ERR-1) Uncertainty due to half life of Sc-46. 2361700200013 (ERR-2) Uncertainty due to gamma-ray emission 2361700200014 probability. 2361700200015 (ERR-3) Uncertainty due to relative gamma-ray 2361700200016 efficiency of the Ge-detector. 2361700200017 (ERR-4) Uncertainty due to sample weight. 2361700200018 (ERR-5) Uncertainty due to sample purity. 2361700200019 (ERR-6) Uncertainty due to irradiation time. 2361700200020 (ERR-7) Uncertainty due to the thermal neutron flux. 2361700200021 (5.904+-0.050)E+10(n/cm2/sec) 2361700200022 STATUS (TABLE,,S.Nakamura+,J,NST,61,1415,2024) Tables 6, 7, 8 2361700200023 At the request of the author, the uncertainty due to 2361700200024 sample purity, ERR-5, was revised from 0.1001 2361700200025 to 0.1000. 2361700200026 ENDBIB 24 0 2361700200027 COMMON 8 6 2361700200028 ERR-S ERR-1 ERR-2 ERR-3 ERR-4 ERR-5 2361700200029 ERR-6 ERR-7 2361700200030 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2361700200031 PER-CENT PER-CENT 2361700200032 0.5195 0.0191 0.0003 0.2416 0.0926 0.10002361700200033 0.0278 0.8469 2361700200034 ENDCOMMON 6 0 2361700200035 DATA 3 1 2361700200036 EN DATA ERR-T 2361700200037 MILLI-EV B B 2361700200038 25.3 27.18 0.28 2361700200039 ENDDATA 3 0 2361700200040 ENDSUBENT 39 0 2361700299999 SUBENT 23617003 20250219 23212361700300001 BIB 5 22 2361700300002 REACTION (29-CU-63(N,G)29-CU-64,,SIG) 2361700300003 SAMPLE (29-CU-63,NAT=0.6915) 2361700300004 Sample: Cu-nat metal foil 3.271+-0.001 mg 2361700300005 Monitor: Co-nat metal foil 0.631+-0.001 mg 2361700300006 Mo-nat metal foil 8.351+-0.001 mg 2361700300007 Au/Al Alloy wire 4.441+-0.001 mg 2361700300008 DECAY-DATA (29-CU-64,12.7004HR,DG,1345.77,0.004748) 2361700300009 ERR-ANALYS (ERR-T) Total uncertainty. 2361700300010 (ERR-S) Statistical uncertainty. 2361700300011 (2.5632+-0.0233)E-13 (event/s) 2361700300012 (ERR-1) Uncertainty due to half life of Sc-46. 2361700300013 (ERR-2) Uncertainty due to gamma-ray emission 2361700300014 probability. 2361700300015 (ERR-3) Uncertainty due to relative gamma-ray 2361700300016 efficiency of the Ge-detector. 2361700300017 (ERR-4) Uncertainty due to sample weight. 2361700300018 (ERR-5) Uncertainty due to sample purity. 2361700300019 (ERR-6) Uncertainty due to irradiation time. 2361700300020 (ERR-7) Uncertainty due to isotopic abundance. 2361700300021 (ERR-8) Uncertainty due to the thermal neutron flux. 2361700300022 (5.904+-0.050)E+10(n/cm2/sec) 2361700300023 STATUS (TABLE,,S.Nakamura+,J,NST,61,1415,2024) Tables 6, 7, 9 2361700300024 ENDBIB 22 0 2361700300025 COMMON 9 6 2361700300026 ERR-S ERR-1 ERR-2 ERR-3 ERR-4 ERR-5 2361700300027 ERR-6 ERR-7 ERR-8 2361700300028 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2361700300029 PER-CENT PER-CENT PER-CENT 2361700300030 0.9090 0.0157 0.7161 0.3634 0.0306 0.01002361700300031 0.1157 0.0278 0.8469 2361700300032 ENDCOMMON 6 0 2361700300033 DATA 3 1 2361700300034 EN DATA ERR-T 2361700300035 MILLI-EV B B 2361700300036 25.3 4.34 0.06 2361700300037 ENDDATA 3 0 2361700300038 ENDSUBENT 37 0 2361700399999 SUBENT 23617004 20250219 23212361700400001 BIB 5 21 2361700400002 REACTION (30-ZN-64(N,G)30-ZN-65,,SIG) 2361700400003 SAMPLE (30-ZN-64,NAT=0.4917) 2361700400004 Sample: Zn-nat metal foil 24.856+-0.001 mg 2361700400005 Monitor: Co-nat metal foil 0.617+-0.001 mg 2361700400006 Au/Al Alloy wire 4.928+-0.001 mg 2361700400007 DECAY-DATA (30-ZN-65,244.01D,DG,1115.55,0.5022) 2361700400008 ERR-ANALYS (ERR-T) Total uncertainty. 2361700400009 (ERR-S) Statistical uncertainty. 2361700400010 (4.4786+-0.0401)E-14 (event/s) 2361700400011 (ERR-1) Uncertainty due to half life of Sc-46. 2361700400012 (ERR-2) Uncertainty due to gamma-ray emission 2361700400013 probability. 2361700400014 (ERR-3) Uncertainty due to relative gamma-ray 2361700400015 efficiency of the Ge-detector. 2361700400016 (ERR-4) Uncertainty due to sample weight. 2361700400017 (ERR-5) Uncertainty due to sample purity. 2361700400018 (ERR-6) Uncertainty due to irradiation time. 2361700400019 (ERR-7) Uncertainty due to isotopic abundance. 2361700400020 (ERR-8) Uncertainty due to the thermal neutron flux. 2361700400021 (6.205+-0.053)E+10(n/cm2/sec) 2361700400022 STATUS (TABLE,,S.Nakamura+,J,NST,61,1415,2024) Tables 6, 7, 102361700400023 ENDBIB 21 0 2361700400024 COMMON 9 6 2361700400025 ERR-S ERR-1 ERR-2 ERR-3 ERR-4 ERR-5 2361700400026 ERR-6 ERR-7 ERR-8 2361700400027 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2361700400028 PER-CENT PER-CENT PER-CENT 2361700400029 0.8954 0.0369 0.2190 0.2377 0.0040 0.01002361700400030 0.7728 0.0278 0.8541 2361700400031 ENDCOMMON 6 0 2361700400032 DATA 3 1 2361700400033 EN DATA ERR-T 2361700400034 MILLI-EV B B 2361700400035 25.3 0.719 0.011 2361700400036 ENDDATA 3 0 2361700400037 ENDSUBENT 36 0 2361700499999 SUBENT 23617005 20250219 23212361700500001 BIB 5 21 2361700500002 REACTION (30-ZN-68(N,G)30-ZN-69-M,,SIG) 2361700500003 SAMPLE (30-ZN-68,NAT=0.1845) 2361700500004 Sample: Zn-nat metal foil 24.856+-0.001 mg 2361700500005 Monitor: Co-nat metal foil 0.617+-0.001 mg 2361700500006 Au/Al Alloy wire 4.928+-0.001 mg 2361700500007 DECAY-DATA (30-ZN-69-M,13.76HR,DG,438.63,0.9477) 2361700500008 ERR-ANALYS (ERR-T) Total uncertainty. 2361700500009 (ERR-S) Statistical uncertainty. 2361700500010 (4.5882+-0.0140)E-15 (event/s) 2361700500011 (ERR-1) Uncertainty due to half life of Sc-46. 2361700500012 (ERR-2) Uncertainty due to gamma-ray emission 2361700500013 probability. 2361700500014 (ERR-3) Uncertainty due to relative gamma-ray 2361700500015 efficiency of the Ge-detector. 2361700500016 (ERR-4) Uncertainty due to sample weight. 2361700500017 (ERR-5) Uncertainty due to sample purity. 2361700500018 (ERR-6) Uncertainty due to irradiation time. 2361700500019 (ERR-7) Uncertainty due to isotopic abundance. 2361700500020 (ERR-8) Uncertainty due to the thermal neutron flux. 2361700500021 (6.205+-0.053)E+10(n/cm2/sec) 2361700500022 STATUS (TABLE,,S.Nakamura+,J,NST,61,1415,2024) Tables 6, 7, 112361700500023 ENDBIB 21 0 2361700500024 COMMON 9 6 2361700500025 ERR-S ERR-1 ERR-2 ERR-3 ERR-4 ERR-5 2361700500026 ERR-6 ERR-7 ERR-8 2361700500027 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2361700500028 PER-CENT PER-CENT PER-CENT 2361700500029 0.3051 0.1453 0.0317 0.9861 0.0040 0.01002361700500030 1.7344 0.0278 0.8541 2361700500031 ENDCOMMON 6 0 2361700500032 DATA 3 1 2361700500033 EN DATA ERR-T 2361700500034 MILLI-EV B B 2361700500035 25.3 0.0737 0.0017 2361700500036 ENDDATA 3 0 2361700500037 ENDSUBENT 36 0 2361700599999 SUBENT 23617006 20250219 23212361700600001 BIB 5 26 2361700600002 REACTION (47-AG-109(N,G)47-AG-110-M,,SIG) 2361700600003 SAMPLE (47-AG-109,NAT=0.48161) 2361700600004 Sample: Ag-nat metal foil 1.395+-0.001 mg 2361700600005 Monitor: Co-nat metal foil 0.631+-0.001 mg 2361700600006 Mo-nat metal foil 8.351+-0.001 mg 2361700600007 Au/Al Alloy wire 4.441+-0.001 mg 2361700600008 DECAY-DATA (47-AG-110-M,249.78D,DG,657.76,0.9438, 2361700600009 DG,884.68,0.740) 2361700600010 ERR-ANALYS (ERR-T) Total uncertainty. 2361700600011 (ERR-S) Statistical uncertainty. 2361700600012 (2.4018+-0.0164)E-13 (event/s) 2361700600013 (ERR-1) Uncertainty due to half life of Sc-46. 2361700600014 (ERR-2) Uncertainty due to gamma-ray emission 2361700600015 probability. 2361700600016 (ERR-3) Uncertainty due to relative gamma-ray 2361700600017 efficiency of the Ge-detector. 2361700600018 (ERR-4) Uncertainty due to sample weight. 2361700600019 (ERR-5) Uncertainty due to sample purity. 2361700600020 (ERR-6) Uncertainty due to irradiation time. 2361700600021 (ERR-7) Uncertainty due to isotopic abundance. 2361700600022 (ERR-8) Uncertainty due to the thermal neutron flux. 2361700600023 (5.904+-0.050)E+10(n/cm2/sec) 2361700600024 STATUS (TABLE,,S.Nakamura+,J,NST,61,1415,2024) Tables 6, 7, 122361700600025 In Table 2 and Table 6, one of the decay gamma-ray 2361700600026 energies from Ag-110m do not match. At the author's 2361700600027 request, the value in Table 2 was adopted. 2361700600028 ENDBIB 26 0 2361700600029 COMMON 9 6 2361700600030 ERR-S ERR-1 ERR-2 ERR-3 ERR-4 ERR-5 2361700600031 ERR-6 ERR-7 ERR-8 2361700600032 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2361700600033 PER-CENT PER-CENT PER-CENT 2361700600034 0.6828 0.0080 0.0848 0.4767 0.0717 0.01002361700600035 0.0083 0.0278 0.8469 2361700600036 ENDCOMMON 6 0 2361700600037 DATA 3 1 2361700600038 EN DATA ERR-T 2361700600039 MILLI-EV B B 2361700600040 25.3 4.05 0.05 2361700600041 ENDDATA 3 0 2361700600042 ENDSUBENT 41 0 2361700699999 SUBENT 23617007 20250219 23212361700700001 BIB 5 23 2361700700002 REACTION (49-IN-113(N,G)49-IN-114-M,,SIG) 2361700700003 SAMPLE (49-IN-113,NAT=0.04256) 2361700700004 Sample: In-nat metal foil 9.171+-0.001 mg 2361700700005 Monitor: Co-nat metal foil 0.631+-0.001 mg 2361700700006 Mo-nat metal foil 8.351+-0.001 mg 2361700700007 Au/Al Alloy wire 4.441+-0.001 mg 2361700700008 DECAY-DATA (49-IN-114-M,49.51D,DG,190.34,0.1556) 2361700700009 ERR-ANALYS (ERR-T) Total uncertainty. 2361700700010 (ERR-S) Statistical uncertainty. 2361700700011 (4.9160+-0.0507)E-13 (event/s) 2361700700012 (ERR-1) Uncertainty due to half life of Sc-46. 2361700700013 (ERR-2) Uncertainty due to gamma-ray emission 2361700700014 probability. 2361700700015 (ERR-3) Uncertainty due to relative gamma-ray 2361700700016 efficiency of the Ge-detector. 2361700700017 (ERR-4) Uncertainty due to sample weight. 2361700700018 (ERR-5) Uncertainty due to sample purity. 2361700700019 (ERR-6) Uncertainty due to irradiation time. 2361700700020 (ERR-7) Uncertainty due to isotopic abundance. 2361700700021 (ERR-8) Uncertainty due to the thermal neutron flux. 2361700700022 (5.904+-0.050)E+10(n/cm2/sec) 2361700700023 STATUS (TABLE,,S.Nakamura+,J,NST,61,1415,2024) Tables 6, 7, 132361700700024 Data were obtained from AUTHOR 2361700700025 ENDBIB 23 0 2361700700026 COMMON 9 6 2361700700027 ERR-S ERR-1 ERR-2 ERR-3 ERR-4 ERR-5 2361700700028 ERR-6 ERR-7 ERR-8 2361700700029 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2361700700030 PER-CENT PER-CENT PER-CENT 2361700700031 1.0313 0.0202 0.9640 2.7136 0.0109 0.00102361700700032 0.0470 0.0278 0.8469 2361700700033 ENDCOMMON 6 0 2361700700034 DATA 3 1 2361700700035 EN DATA ERR-T 2361700700036 MILLI-EV B B 2361700700037 25.3 8.53 0.27 2361700700038 ENDDATA 3 0 2361700700039 ENDSUBENT 38 0 2361700799999 ENDENTRY 7 0 2361799999999