ENTRY 23611 20231211 23212361100000001 SUBENT 23611001 20231211 23212361100100001 BIB 15 63 2361100100002 TITLE Measurements of capture cross-section of 93Nb by 2361100100003 activation method and half-life of 94Nb by mass 2361100100004 analysis 2361100100005 AUTHOR (S.Nakamura,Y.Shibahara,S.Endo,A.Kimura) 2361100100006 INSTITUTE (2JPNJAE,2JPNKTO) 2361100100007 REFERENCE (J,NST,60,1361,2023) 2361100100008 #doi:10.1080/00223131.2023.2198526 2361100100009 FACILITY (REAC,2JPNKTO) 2361100100010 Kyoto University Research Reactor (KUR). 2361100100011 INC-SOURCE (REAC) Hydraulic Conveyor of KUR, 2361100100012 nominal: 1E+14 (n/cm2sec) under 5MW operation. 2361100100013 SAMPLE The niobium samples were metal foils with a purity of 2361100100014 99.99%; each had a diameter of 4 mm, a thickness of 2361100100015 0.054 mm, and a mass in the order of 5 mg. 2361100100016 DETECTOR (HPGE) Decay gamma rays were measured with a high- 2361100100017 purity Ge detector relative efficiency of 25%. 2361100100018 The gamma-ray peak efficiencies of the Ge detector were2361100100019 measured using a mixed source AM-8140: Am-241, Cd-109, 2361100100020 Co-57, Ce-139, Hg-203, Sn-113, Cs-137, Co-60 and Y-88. 2361100100021 METHOD (ACTIV,GSPEC) Based on the Westcott convention method 2361100100022 with Cadmium-difference method. 2361100100023 To set 0.133 eV as cut-off energy, Gd foils with 2361100100024 thickness of 25 micro-meter was used as neutron filter.2361100100025 Au/Al alloy and Co/Al alloy were used as monitor 2361100100026 materials to determine neutron fluxes. 2361100100027 The bare and Gd filtered samples were irradiated for 2361100100028 6 hours in the hydraulic conveyor. 2361100100029 After nearly 2 years cooling, the decay gamma-rays 2361100100030 from the Nb samples were measured for 10 h for the 2361100100031 bare condition and 15 h for the Gd filtered condition. 2361100100032 ANALYSIS The weighted averages of the reaction rates in the Nb 2361100100033 samples were derived using 703-, and 871-keV 2361100100034 gamma rays. 2361100100035 At the time of the gamma-ray measurement, the isomer 2361100100036 94mNb (Half life: 6.263 min) had fully decayed to 2361100100037 94gNb (Transition Ratio: 99.5%). 2361100100038 The thermal and epi-thermal neutron flux was derived 2361100100039 using the reaction rates, the thermal cross sections, 2361100100040 the resonance integral cross sections, and the 2361100100041 g-factors of the monitor materials. 2361100100042 These values were taken from the REL-REF. 2361100100043 Based on Westcott convention, thermal cross section 2361100100044 and resonance integral were deduced. 2361100100045 The g-factor of 93Nb (1.003) was taken from the 2361100100046 REL-REF. 2361100100047 DECAY-DATA (79-AU-198-G,2.6943D,DG,411.80,0.9562) 2361100100048 (27-CO-60-G,5.2711YR,DG,1173.24,0.99826, 2361100100049 DG,1332.50,0.9985) 2361100100050 (41-NB-94-G,2.04E+04YR,DG,871.1,0.999, 2361100100051 DG,702.6,0.979) 2361100100052 ASSUMED Values assumed to deduce the thermal and epi-thermal 2361100100053 neutron fluxes. 2361100100054 (ASSUM1,27-CO-59(N,G)27-CO-60,,SIG) Thermal C.S. 2361100100055 (ASSUM2,27-CO-59(N,G)27-CO-60,,RI) 2361100100056 (ASSUM3,79-AU-197(N,G)79-AU-198,,SIG) Thermal C.S. 2361100100057 (ASSUM4,79-AU-197(N,G)79-AU-198,,RI) 2361100100058 ERR-ANALYS (ASSUM1-ERR) Uncertainty of Au-197 thermal C.S. 2361100100059 (ASSUM2-ERR) Uncertainty of Au-197 RI. 2361100100060 (ASSUM3-ERR) Uncertainty of Co-59 thermal C.S. 2361100100061 (ASSUM4-ERR) Uncertainty of Co-59 RI. 2361100100062 REL-REF (R,,S.F.Mughabghab,B,NEUT.RES,,,2018) Thermal capture 2361100100063 cross sections of monitors and g-factors were given. 2361100100064 HISTORY (20231211C) By A. Kimura 2361100100065 ENDBIB 63 0 2361100100066 COMMON 8 6 2361100100067 ASSUM1 ASSUM1-ERR ASSUM2 ASSUM2-ERR ASSUM3 ASSUM3-ERR 2361100100068 ASSUM4 ASSUM4-ERR 2361100100069 B B B B B B 2361100100070 B B 2361100100071 98.65 0.09 1550. 28. 37.18 0.062361100100072 75.8 2.0 2361100100073 ENDCOMMON 6 0 2361100100074 ENDSUBENT 73 0 2361100199999 SUBENT 23611002 20231211 23212361100200001 BIB 3 19 2361100200002 REACTION (41-NB-93(N,G)41-NB-94,,SIG) 2361100200003 ERR-ANALYS (ERR-T) Total Uncertainty 2361100200004 (ERR-1) Uncertainty due to statistical uncertainty of 2361100200005 gamma-ray yields of 94gNb. 2361100200006 (ERR-2) Uncertainty due to half-life of 94gNb. 2361100200007 (ERR-3) Uncertainty due to emission probabilities. 2361100200008 (ERR-4) Uncertainty due to isomer transition. 2361100200009 (ERR-5) Uncertainty due to gamma detection efficiency 2361100200010 (ERR-6) Uncertainty due to sample weight. 2361100200011 (ERR-7) Uncertainty due to irradiation time. 2361100200012 (ERR-8) Uncertainty due to thermal neutron flux 2361100200013 without the Gd filter. 2361100200014 (ERR-9) Uncertainty due to epi-thermal neutron flux 2361100200015 without the Gd filter. 2361100200016 (ERR-10) Uncertainty due to sensitivity to epi-thermal 2361100200017 neutrons(s0). 2361100200018 STATUS (TABLE,,S.Nakamura+,J,NST,60,1361,2023) Tables 5,6,7 2361100200019 Data were provided by AUTHOR. 2361100200020 (COREL,23611003) Resonance integral data. 2361100200021 ENDBIB 19 0 2361100200022 COMMON 10 6 2361100200023 ERR-1 ERR-2 ERR-3 ERR-4 ERR-5 ERR-6 2361100200024 ERR-7 ERR-8 ERR-9 ERR-10 2361100200025 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2361100200026 PER-CENT PER-CENT PER-CENT PER-CENT 2361100200027 1.00 1.96 0.1 0.5 1.68 0.022361100200028 0.46 1.10 1.10 1.30 2361100200029 ENDCOMMON 6 0 2361100200030 DATA 3 1 2361100200031 EN DATA ERR-T 2361100200032 EV B B 2361100200033 0.0253 1.11 0.04 2361100200034 ENDDATA 3 0 2361100200035 ENDSUBENT 34 0 2361100299999 SUBENT 23611003 20231211 23212361100300001 BIB 3 16 2361100300002 REACTION (41-NB-93(N,G)41-NB-94,,RI) 2361100300003 ERR-ANALYS (ERR-T) Total Uncertainty 2361100300004 (ERR-1) Uncertainty due to ratio of Nb gamma-ray yields2361100300005 with/without the Gd filter. 2361100300006 (ERR-2) Uncertainty due to thermal neutron flux 2361100300007 without the Gd filter. 2361100300008 (ERR-3) Uncertainty due to EPI-thermal neutron flux 2361100300009 without the Gd filter. 2361100300010 (ERR-4) Uncertainty due to thermal neutron flux 2361100300011 with the Gd filter. 2361100300012 (ERR-5) Uncertainty due to epi-thermal neutron flux 2361100300013 with the Gd filter. 2361100300014 (ERR-6) Uncertainty due to thermal cross section 2361100300015 STATUS (TABLE,,S.Nakamura+,J,NST,60,1361,2023) Tables 6 and 7 2361100300016 Data were provided by AUTHOR. 2361100300017 (COREL,23611002) Thermal cross section is given. 2361100300018 ENDBIB 16 0 2361100300019 COMMON 6 3 2361100300020 ERR-1 ERR-2 ERR-3 ERR-4 ERR-5 ERR-6 2361100300021 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2361100300022 0.1 2.1 2.1 1.4 3.5 3.62361100300023 ENDCOMMON 3 0 2361100300024 DATA 3 1 2361100300025 EN-MIN DATA ERR-T 2361100300026 EV B B 2361100300027 0.133 10.5 0.6 2361100300028 ENDDATA 3 0 2361100300029 ENDSUBENT 28 0 2361100399999 SUBENT 23611004 20231211 23212361100400001 BIB 4 19 2361100400002 REACTION (41-NB-93(N,G)41-NB-94,,RI,,,DERIV) 2361100400003 ANALYSIS Based on Westcott convention method, the resonance 2361100400004 integral for cut-off energy 0.5 eV was calculated. 2361100400005 See Eq. (3) and (4) in the REFERENCE. 2361100400006 ERR-ANALYS (ERR-T) Total Uncertainty 2361100400007 (ERR-1) Uncertainty due to ratio of Nb gamma-ray yield2361100400008 with/without the Gd filter. 2361100400009 (ERR-2) Uncertainty due to thermal neutron flux 2361100400010 without the Gd filter. 2361100400011 (ERR-3) Uncertainty due to epi-thermal neutron flux 2361100400012 without the Gd filter. 2361100400013 (ERR-4) Uncertainty due to thermal neutron flux 2361100400014 with the Gd filter. 2361100400015 (ERR-5) Uncertainty due to epi-thermal neutron flux 2361100400016 with the Gd filter. 2361100400017 (ERR-6) Uncertainty due to thermal cross section 2361100400018 STATUS (TABLE,,S.Nakamura+,J,NST,60,1361,2023) Tables 6 and 7 2361100400019 Data were provided by AUTHOR. 2361100400020 (DEP,23611003) Data with Cut-off Energy of 0.133 eV. 2361100400021 ENDBIB 19 0 2361100400022 COMMON 6 3 2361100400023 ERR-1 ERR-2 ERR-3 ERR-4 ERR-5 ERR-6 2361100400024 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2361100400025 0.1 2.2 2.2 1.5 3.6 3.62361100400026 ENDCOMMON 3 0 2361100400027 DATA 3 1 2361100400028 EN-MIN DATA ERR-T 2361100400029 EV B B 2361100400030 0.5 10.1 0.6 2361100400031 ENDDATA 3 0 2361100400032 ENDSUBENT 31 0 2361100499999 ENDENTRY 4 0 2361199999999