ENTRY 23619 20250225 23212361900000001 SUBENT 23619001 20250225 23212361900100001 BIB 16 63 2361900100002 TITLE Measurements of neutron capture cross-section for 2361900100003 nuclides of interest in decommissioning (III) : 2361900100004 170Er(n,gamma)171Er and 180Hf(n,gamma) 181Hf reactions 2361900100005 AUTHOR (S.Nakamura,Y.Shibahara,S.Endo,G.Rovira,A.Kimura) 2361900100006 INSTITUTE (2JPNJAE,2JPNKTO) 2361900100007 REFERENCE (J,NST,62,617,2025) 2361900100008 #doi:10.1080/00223131.2025.2457589 2361900100009 FACILITY (REAC,2JPNKTO) 2361900100010 Kyoto University Research Reactor (KUR) . 2361900100011 INC-SOURCE (REAC)The graphite thermal column (TC-Pn) in KUR. 2361900100012 The nominal neutron flux intensity of TC-Pn is 2361900100013 5.86E+10 (n/cm2/sec) at 1 MW power operation. 2361900100014 The AUTHORs confirmed that the TC-Pn was well 2361900100015 thermalized in the previous experiment. 2361900100016 See Fig. 9 in J,NST,58,1061,2021 (REL-REF) . 2361900100017 METHOD (ACTIV,GSPEC) Based on Westcott convention method. 2361900100018 Samples and monitors were irradiated in the TC-Pn 2361900100019 for 1 hour under 1-MW power operation. 2361900100020 The decay gamma-rays were measured with a germanium 2361900100021 detector. 2361900100022 DETECTOR (HPGE) High purity germanium detector, relative 2361900100023 efficiency of 25%. 2361900100024 The gamma-ray peak efficiencies of the Ge detector 2361900100025 were measured using a Eu-152 source and a mixed source 2361900100026 AM-8140 (Am-241, Cd-109, Co-57, Ce-139, Hg-203, 2361900100027 Sn-113, Cs-137, Co-60 and Y-88) . 2361900100028 The uncertainty in the source radioactivity was 1.5% 2361900100029 for both of the standard sources. 2361900100030 ANALYSIS The reaction rates of the target reactions were 2361900100031 obtained from the yields of the gamma rays emitted 2361900100032 from the irradiated samples. 2361900100033 The thermal-neutron fluxes were derived using neutron 2361900100034 flux monitors: Au-197 and Co-59. 2361900100035 - For the Er sample: (5.326+-0.086)E+10 (n/cm2/sec) 2361900100036 - For the Hf sample: (5.411+-0.087)E+10 (n/cm2/sec) 2361900100037 Because the neutron flux in the TC-Pn is well 2361900100038 thermalized, epithermal component in Westcott 2361900100039 convention method was negligibly small. 2361900100040 The capture cross sections were derived using 2361900100041 the reaction rates and the thermal-neutron fluxes. 2361900100042 The thermal capture cross sections for monitors and 2361900100043 the g-factors were taken from REL-REF. 2361900100044 CORRECTION Self-shielding coefficients for thermal neutrons were 2361900100045 calculated from neutron capture cross-sections and 2361900100046 area densities of the sample and the monitors. The 2361900100047 coincidence summing effect was estimated from the 2361900100048 peak-to-total ratios and the peak efficiencies. 2361900100049 DECAY-DATA (79-AU-198-G,2.6943D,DG,411.80,0.9562) 2361900100050 (27-CO-60-G,5.2711YR,DG,1173.24,0.9985, 2361900100051 DG,1332.49,0.99826) 2361900100052 ASSUMED Thermal capture cross sections of the monitors were 2361900100053 assumed to be well known to determine the thermal 2361900100054 neutron flux. 2361900100055 (ASSUM1,79-AU-197(N,G)79-AU-198,,SIG) 2361900100056 (ASSUM2,27-CO-59(N,G)27-CO-60,,SIG) 2361900100057 ERR-ANALYS (ASSUM1-ERR) Uncertainty of Au-197 thermal C.S. 2361900100058 (ASSUM2-ERR) Uncertainty of Co-59 thermal C.S. 2361900100059 REL-REF (R,,S.F.Mughabghab,B,NEUT.RES,,,2018) Thermal capture 2361900100060 cross section of the monitors and g-factor were given. 2361900100061 (I,,S.Nakamura+,J,NST,58,1061,2021) The reference to 2361900100062 show that the irradiation field is well thermalized. 2361900100063 STATUS (APRVD) Proofread by Shoji Nakamura. (2025-02-22) 2361900100064 HISTORY (20250225C) By A.Kimura. 2361900100065 ENDBIB 63 0 2361900100066 COMMON 4 3 2361900100067 ASSUM1 ASSUM1-ERR ASSUM2 ASSUM2-ERR 2361900100068 B B B B 2361900100069 98.65 0.09 37.18 0.06 2361900100070 ENDCOMMON 3 0 2361900100071 ENDSUBENT 70 0 2361900199999 SUBENT 23619002 20250225 23212361900200001 BIB 5 22 2361900200002 REACTION (68-ER-170(N,G)68-ER-171,,SIG) 2361900200003 SAMPLE (68-ER-170,NAT=0.14910) 2361900200004 Sample: Er-nat metal foil 3.311+-0.001 mg 2361900200005 Monitor: Co-nat metal foil 0.552+-0.001 mg 2361900200006 Au/Al Alloy wire 4.245+-0.001 mg 2361900200007 DECAY-DATA (68-ER-171,7.516HR,DG,295.90,0.289, 2361900200008 DG,308.31,0.644) 2361900200009 ERR-ANALYS (ERR-T) Total uncertainty. 2361900200010 (ERR-S) Statistical uncertainty. 2361900200011 (4.253+-0.057)E-13 (event/s) 2361900200012 (ERR-1) Uncertainty due to half life of Er-171. 2361900200013 (ERR-2) Uncertainty due to gamma-ray emission 2361900200014 probability. 2361900200015 (ERR-3) Uncertainty due to relative gamma-ray 2361900200016 efficiency of the Ge-detector. 2361900200017 (ERR-4) Uncertainty due to sample weight. 2361900200018 (ERR-5) Uncertainty due to sample purity. 2361900200019 (ERR-6) Uncertainty due to irradiation time. 2361900200020 (ERR-7) Uncertainty due to isotopic abundance. 2361900200021 (ERR-8) Uncertainty due to the thermal neutron flux. 2361900200022 (5.326+-0.032)E+10(n/cm2/sec) 2361900200023 STATUS (TABLE,,S.Nakamura+,J,NST,61,617,2024) Tables 5, 6, 7 2361900200024 ENDBIB 22 0 2361900200025 COMMON 9 6 2361900200026 ERR-S ERR-1 ERR-2 ERR-3 ERR-4 ERR-5 2361900200027 ERR-6 ERR-7 ERR-8 2361900200028 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2361900200029 PER-CENT PER-CENT PER-CENT 2361900200030 1.340 0.014 3.898 0.349 0.030 1.0102361900200031 0.121 0.028 0.601 2361900200032 ENDCOMMON 6 0 2361900200033 DATA 3 1 2361900200034 EN DATA ERR-T 2361900200035 MILLI-EV B B 2361900200036 25.3 8.19 0.35 2361900200037 ENDDATA 3 0 2361900200038 ENDSUBENT 37 0 2361900299999 SUBENT 23619003 20250225 23212361900300001 BIB 5 21 2361900300002 REACTION (72-HF-180(N,G)72-HF-181,,SIG) 2361900300003 SAMPLE (72-HF-180,NAT=0.3508) 2361900300004 Sample: Hf-nat metal foil 4.537+-0.001 mg 2361900300005 Monitor: Co-nat metal foil 0.572+-0.001 mg 2361900300006 Au/Al Alloy wire 4.600+-0.001 mg 2361900300007 DECAY-DATA (72-HF-181,42.39D,DG,482.18,0.805) 2361900300008 ERR-ANALYS (ERR-T) Total uncertainty. 2361900300009 (ERR-S) Statistical uncertainty. 2361900300010 (7.209+-0.032)E-13 (event/s) 2361900300011 (ERR-1) Uncertainty due to half life of Hf-181. 2361900300012 (ERR-2) Uncertainty due to gamma-ray emission 2361900300013 probability. 2361900300014 (ERR-3) Uncertainty due to relative gamma-ray 2361900300015 efficiency of the Ge-detector. 2361900300016 (ERR-4) Uncertainty due to sample weight. 2361900300017 (ERR-5) Uncertainty due to sample purity. 2361900300018 (ERR-6) Uncertainty due to irradiation time. 2361900300019 (ERR-7) Uncertainty due to isotopic abundance. 2361900300020 (ERR-8) Uncertainty due to the thermal neutron flux. 2361900300021 (5.441+-0.032)E+10(n/cm2/sec) 2361900300022 STATUS (TABLE,,S.Nakamura+,J,NST,61,617,2024) Tables 5, 6, 8 2361900300023 ENDBIB 21 0 2361900300024 COMMON 9 6 2361900300025 ERR-S ERR-1 ERR-2 ERR-3 ERR-4 ERR-5 2361900300026 ERR-6 ERR-7 ERR-8 2361900300027 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2361900300028 PER-CENT PER-CENT PER-CENT 2361900300029 0.444 0.142 0.621 0.254 0.022 0.10002361900300030 0.005 0.028 0.588 2361900300031 ENDCOMMON 6 0 2361900300032 DATA 3 1 2361900300033 EN DATA ERR-T 2361900300034 MILLI-EV B B 2361900300035 25.3 13.57 0.14 2361900300036 ENDDATA 3 0 2361900300037 ENDSUBENT 36 0 2361900399999 SUBENT 23619004 20250225 23212361900400001 BIB 5 22 2361900400002 REACTION (72-HF-179(N,G)72-HF-180-M,,SIG) 2361900400003 SAMPLE (72-HF-179,NAT=0.1362) 2361900400004 Sample: Hf-nat metal foil 4.537+-0.001 mg 2361900400005 Monitor: Co-nat metal foil 0.572+-0.001 mg 2361900400006 Au/Al Alloy wire 4.600+-0.001 mg 2361900400007 DECAY-DATA (72-HF-180-M,5.47HR,DG,215.27,0.813,DG,332.28,0.911, 2361900400008 DG,443.09,0.819,DG,500.64,0.143) 2361900400009 ERR-ANALYS (ERR-T) Total uncertainty. 2361900400010 (ERR-S) Statistical uncertainty. 2361900400011 (2.269+-0.012)E-14 (event/s) 2361900400012 (ERR-1) Uncertainty due to half life of Hf-180m. 2361900400013 (ERR-2) Uncertainty due to gamma-ray emission 2361900400014 probability. 2361900400015 (ERR-3) Uncertainty due to relative gamma-ray 2361900400016 efficiency of the Ge-detector. 2361900400017 (ERR-4) Uncertainty due to sample weight. 2361900400018 (ERR-5) Uncertainty due to sample purity. 2361900400019 (ERR-6) Uncertainty due to irradiation time. 2361900400020 (ERR-7) Uncertainty due to isotopic abundance. 2361900400021 (ERR-8) Uncertainty due to the thermal neutron flux. 2361900400022 (5.441+-0.032)E+10(n/cm2/sec) 2361900400023 STATUS (TABLE,,S.Nakamura+,J,NST,61,617,2024) Tables 5, 6, 9 2361900400024 ENDBIB 22 0 2361900400025 COMMON 9 6 2361900400026 ERR-S ERR-1 ERR-2 ERR-3 ERR-4 ERR-5 2361900400027 ERR-6 ERR-7 ERR-8 2361900400028 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2361900400029 PER-CENT PER-CENT PER-CENT 2361900400030 0.529 0.548 0.956 0.331 0.022 0.10002361900400031 0.004 0.028 0.588 2361900400032 ENDCOMMON 6 0 2361900400033 DATA 3 1 2361900400034 EN DATA ERR-T 2361900400035 MILLI-EV B B 2361900400036 25.3 0.427 0.006 2361900400037 ENDDATA 3 0 2361900400038 ENDSUBENT 37 0 2361900499999 ENDENTRY 4 0 2361999999999