ENTRY 23744 20210906 23022374400000001 SUBENT 23744001 20210906 23022374400100001 BIB 14 70 2374400100002 TITLE Thermal-neutron capture cross sections and resonance 2374400100003 integrals of the 243Am(n,g)244gAm and 2374400100004 243Am(n,g)244m+gAm reactions 2374400100005 AUTHOR (S.Nakamura,Y.Shibahara,S.Endo,A.Kimura) 2374400100006 INSTITUTE (2JPNJAE,2JPNKTO) 2374400100007 REFERENCE (J,NST,58,259,2021) 2374400100008 #doi:10.1080/00223131.2020.1819907 2374400100009 FACILITY (REAC,2JPNKTO) 2374400100010 Kyoto University Research Reactor (KUR). 2374400100011 INC-SOURCE (REAC) 2374400100012 -For Am-243(n,g)Am-244g reactions 2374400100013 Pneumatic tube Pn-2, 2374400100014 nominal 1E+12 (n/cm2sec) under 1MW operation. 2374400100015 -For Am-243(n,g)Am-244m+g reactions 2374400100016 Hydraulic Conveyer, 2374400100017 nominal 1E+14 (n/cm2sec) under 5MW operation. 2374400100018 SAMPLE Am-243 standardized solution (2 mol/L(M) HCl) , 2374400100019 which was supplied by Harwell, was used for Am-243 2374400100020 samples. Impurities of the solution were measured with 2374400100021 an alpha-ray spectroscopy. 2374400100022 -Am-243 : Am-241 = 1 : 0.00486. 2374400100023 -Cm-242 and Cm-244 were not observed. 2374400100024 Two Am-243 standardized solutions equivalent to about 2374400100025 1 kBq, were dropped onto pieces of glass filters. 2374400100026 The filters were dried by an infrared ramp. 2374400100027 METHOD (ACTIV,GSPEC,ASPEC) 2374400100028 Based on Westcott's convention method with 2374400100029 Cadmium-difference method. 2374400100030 To set 0.133 eV as cut-off energy, Gd foils with 2374400100031 thickness of 25 micro-meter was used as neutron filter.2374400100032 Au/Al alloy and Co/Al alloy were used as monitor 2374400100033 materials to determine neutron fluxes. 2374400100034 Two sets of bare and Gd-filtered targets were prepared 2374400100035 for different irradiation equipment. 2374400100036 After irradiations, gamma-ray measurements were 2374400100037 performed on the neutron monitors to deduce 2374400100038 neutron fluxes. 2374400100039 For Am-243(n,g)Am-244g reactions, the reaction rate 2374400100040 was deduced with a gamma-ray spectroscopy. 2374400100041 For Am-243(n,g)Am-244m+g reactions, the reaction rate 2374400100042 was deduced with an alpha-ray spectroscopy. 2374400100043 DETECTOR (HPGE,SI) 2374400100044 -For the gamma-ray spectroscopy (monitors and samples 2374400100045 for Am-243(n,g)Am-244g reactions), decay gamma rays 2374400100046 were measured with a high-purity Ge detector 2374400100047 relative efficiency of 25%. 2374400100048 The gamma-ray peak efficiencies of the Ge detector 2374400100049 were measured using a mixed source AM-8140: Am-241, 2374400100050 Cd-109, Co-57, Ce-139, Hg-203, Sn-113, Cs-137, Co-60 2374400100051 and Y-88. 2374400100052 -For the alpha-ray spectroscopy, alpha-rays were 2374400100053 measured with an alpha spectrometer implanted 2374400100054 a silicon detector. 2374400100055 DECAY-DATA (79-AU-198-G,2.6943D,DG,411.80,0.9562) 2374400100056 (27-CO-60-G,5.2711YR,DG,1173.24,0.99826, 2374400100057 DG,1332.50,0.9985) 2374400100058 ASSUMED Values assumed to deduce the thermal and epi-thermal 2374400100059 neutron fluxes. 2374400100060 (ASSUM1,27-CO-59(N,G)27-CO-60,,SIG) Thermal C.S. 2374400100061 (ASSUM2,27-CO-59(N,G)27-CO-60,,RI) 2374400100062 (ASSUM3,79-AU-197(N,G)79-AU-198,,SIG) Thermal C.S. 2374400100063 (ASSUM4,79-AU-197(N,G)79-AU-198,,RI) 2374400100064 ERR-ANALYS (ASSUM1-ERR) Uncertainty of Au-197 thermal C.S. 2374400100065 (ASSUM2-ERR) Uncertainty of Au-197 RI. 2374400100066 (ASSUM3-ERR) Uncertainty of Co-59 thermal C.S. 2374400100067 (ASSUM4-ERR) Uncertainty of Co-59 RI. 2374400100068 REL-REF (R,,S.F.Mughabghab,B,NEUT.RES,,,2018) 2374400100069 Thermal capture cross section and resonance integral 2374400100070 of the monitors were given. 2374400100071 HISTORY (20210903C) Atsushi Kimura 2374400100072 ENDBIB 70 0 2374400100073 COMMON 8 6 2374400100074 ASSUM1 ASSUM1-ERR ASSUM2 ASSUM2-ERR ASSUM3 ASSUM3-ERR 2374400100075 ASSUM4 ASSUM4-ERR 2374400100076 B B B B B B 2374400100077 B B 2374400100078 98.65 0.09 1550. 28. 37.18 0.062374400100079 75.8 2.0 2374400100080 ENDCOMMON 6 0 2374400100081 ENDSUBENT 80 0 2374400199999 SUBENT 23744002 20210906 23022374400200001 BIB 5 37 2374400200002 REACTION (95-AM-243(N,G)95-AM-244-G,,SIG) 2374400200003 ANALYSIS The bare target was irradiated for 30 minutes, and the 2374400200004 Gd filtered target for 5 minutes with Pn-2 in KUR. 2374400200005 After several hours of cooling, gamma-ray measurements 2374400200006 were performed on the Am-243 samples and the monitors. 2374400200007 Neutron flux components were derived from the results 2374400200008 of the monitors. 2374400200009 Because Np-239 (2.356 d) and Am-243 (7,370 yr) are in 2374400200010 radiative equilibrium, the relative number of Am-243 2374400200011 nuclei to Am-244g was determined from the yields of 2374400200012 277.59-keV gamma-rays from Np-239 and 743.97-keV 2374400200013 gamma-rays from Am-244g. 2374400200014 On the basis of Westcott's convention, thermal cross 2374400200015 section and resonance integral were deduced. 2374400200016 DECAY-DATA (95-AM-244-G,10.1HR,DG,743.97,0.665) 2374400200017 (93-NP-239,2.356D,DG,277.59,0.144) 2374400200018 ERR-ANALYS (ERR-T) Total uncertainty. 2374400200019 (ERR-1) Uncertainty due to Half-life of Am-243. 2374400200020 7367 +- 23 (yr) 2374400200021 (ERR-2) Uncertainty due to gamma-ray emission 2374400200022 probability of 277-keV gamma-rays. 2374400200023 14.4 +- 0.1 % 2374400200024 (ERR-3) Uncertainty due to relative gamma-ray 2374400200025 efficiency of the Ge-detector for 277 keV 2374400200026 gamma-rays. 2374400200027 0.5032 +- 0.0019% 2374400200028 (ERR-4) Uncertainty due to Half-life of Am-244g. 2374400200029 10.1 +- 0.1 (h) 2374400200030 (ERR-5) Uncertainty due to gamma-ray emission 2374400200031 probability of 744-keV gamma-rays. 2374400200032 66.5 +- 1.1 % 2374400200033 (ERR-6) Uncertainty due to relative gamma-ray 2374400200034 efficiency of the Ge-detector for 744 keV 2374400200035 gamma-rays. 2374400200036 0.2261 +- 0.0004% 2374400200037 STATUS (TABLE) Tables 7+8 of J.Nucl.Sci.Technol.58(2021)259. 2374400200038 Data were obtained from AUTHOR. 2374400200039 ENDBIB 37 0 2374400200040 COMMON 6 3 2374400200041 ERR-1 ERR-2 ERR-3 ERR-4 ERR-5 ERR-6 2374400200042 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2374400200043 0.31 0.69 0.38 0.48 1.63 0.182374400200044 ENDCOMMON 3 0 2374400200045 DATA 3 1 2374400200046 EN DATA ERR-T 2374400200047 EV B B 2374400200048 0.0253 4.73 0.27 2374400200049 ENDDATA 3 0 2374400200050 ENDSUBENT 49 0 2374400299999 SUBENT 23744003 20210906 23022374400300001 BIB 5 36 2374400300002 REACTION (95-AM-243(N,G)95-AM-244-G,,RI) 2374400300003 ANALYSIS The bare target was irradiated for 30 minutes, and the 2374400300004 Gd filtered target for 5 minutes with Pn-2 in KUR. 2374400300005 After several hours of cooling, gamma-ray measurements 2374400300006 were performed on the Am-243 samples and the monitors. 2374400300007 Neutron flux components were derived from the results 2374400300008 of the monitors. 2374400300009 Because Np-239 (2.356 d) and Am-243 (7,370 yr) are in 2374400300010 radiative equilibrium, the relative number of Am-244g 2374400300011 nuclei to Am-243 was determined from the yields of 2374400300012 277.59-keV gamma-rays from Np-239 and 743.97-keV 2374400300013 gamma-rays from Am-244g. 2374400300014 On the basis of Westcott's convention, thermal cross 2374400300015 section and resonance integral were deduced. 2374400300016 DECAY-DATA (95-AM-244-G,10.1HR,DG,743.97,0.665) 2374400300017 (93-NP-239,2.356D,DG,277.59,0.144) 2374400300018 ERR-ANALYS (ERR-T) Total uncertainty. 2374400300019 (ERR-1) Uncertainty due to Half-life of Am-243. 2374400300020 7367 +- 23 (yr) 2374400300021 (ERR-2) Uncertainty due to gamma-ray emission 2374400300022 probability of 277-keV gamma-rays. 2374400300023 14.4 +- 0.1 % 2374400300024 (ERR-3) Uncertainty due to relative gamma-ray 2374400300025 efficiency of the Ge-detector for 277 keV 2374400300026 gamma-rays. 2374400300027 0.5032 +- 0.0019% 2374400300028 (ERR-4) Uncertainty due to Half-life of Am-244g. 2374400300029 10.1 +- 0.1 (h) 2374400300030 (ERR-5) Uncertainty due to gamma-ray emission 2374400300031 probability of 744-keV gamma-rays. 2374400300032 66.5 +- 1.1 % 2374400300033 (ERR-6) Uncertainty due to relative gamma-ray 2374400300034 efficiency of the Ge-detector for 744 keV 2374400300035 gamma-rays. 2374400300036 0.2261 +- 0.0004% 2374400300037 STATUS (TABLE) Tables 7+8 of J.Nucl.Sci.Technol.58(2021)259. 2374400300038 ENDBIB 36 0 2374400300039 COMMON 6 3 2374400300040 ERR-1 ERR-2 ERR-3 ERR-4 ERR-5 ERR-6 2374400300041 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2374400300042 0.31 0.69 0.38 0.48 1.63 0.182374400300043 ENDCOMMON 3 0 2374400300044 DATA 3 1 2374400300045 EN-MIN DATA ERR-T 2374400300046 EV B B 2374400300047 0.133 96.5 8.9 2374400300048 ENDDATA 3 0 2374400300049 ENDSUBENT 48 0 2374400399999 SUBENT 23744004 20210906 23022374400400001 BIB 5 29 2374400400002 REACTION (95-AM-243(N,G)95-AM-244,,SIG) 2374400400003 ANALYSIS The bare and Gd filtered targets were irradiated 2374400400004 for 6 hours in the hydraulic conveyer under 5-MW power 2374400400005 operation. 2374400400006 The amount of produced Am-244m+g was obtained from the 2374400400007 accumulation in Cm-244. 2374400400008 After 5 days cooling, the relative number of produced 2374400400009 Am-244m+g nuclei to Am-243 nuclei was determined 2374400400010 using the yields of alpha-ray from Cm-244 and that 2374400400011 from Am-243. 2374400400012 Gamma-ray measurements were also performed on the 2374400400013 monitors. Neutron flux components were derived from 2374400400014 the results of the monitors. 2374400400015 On the basis of Westcott's convention, thermal cross 2374400400016 section and resonance integral were deduced. 2374400400017 DECAY-DATA (96-CM-244,18.10YR,A,5804.,0.764, 2374400400018 A,5762.,0.236) 2374400400019 (95-AM-243,7367.YR,A,5275.,0.874, 2374400400020 A,5233.,0.110, 2374400400021 A,5181.,0.011) 2374400400022 ERR-ANALYS (ERR-T) Total uncertainty. 2374400400023 (ERR-1) Uncertainty due to Half-life of Am-243. 2374400400024 7367 +- 23 (yr) 2374400400025 (ERR-2) Uncertainty due to Half-life of Cm-244. 2374400400026 18.10 +- 0.02 (yr) 2374400400027 (ERR-3) Uncertainty due to irradiation time. 2374400400028 19595 +- 90 (sec) 2374400400029 STATUS (TABLE) Tables 11+12 of J.Nucl.Sci.Technol.58(2021)259.2374400400030 Data were provided by AUTHOR. 2374400400031 ENDBIB 29 0 2374400400032 COMMON 3 3 2374400400033 ERR-1 ERR-2 ERR-3 2374400400034 PER-CENT PER-CENT PER-CENT 2374400400035 0.31 0.11 0.46 2374400400036 ENDCOMMON 3 0 2374400400037 DATA 3 1 2374400400038 EN DATA ERR-T 2374400400039 EV B B 2374400400040 0.0253 88.5 4.0 2374400400041 ENDDATA 3 0 2374400400042 ENDSUBENT 41 0 2374400499999 SUBENT 23744005 20210906 23022374400500001 BIB 5 28 2374400500002 REACTION (95-AM-243(N,G)95-AM-244,,RI) 2374400500003 ANALYSIS The bare and Gd filtered targets were irradiated 2374400500004 for 6 hours in the hydraulic conveyer under 5-MW power 2374400500005 operation. 2374400500006 The amount of produced Am-244m+g was obtained from the 2374400500007 accumulation in Cm-244. 2374400500008 After 5 days cooling, the relative number of produced 2374400500009 Am-244m+g nuclei to Am-243 nuclei was determined 2374400500010 using the yields of alpha-ray from Cm-244 and that 2374400500011 from Am-243. 2374400500012 Gamma-ray measurements were also performed on the 2374400500013 monitors. Neutron flux components were derived from 2374400500014 the results of the monitors. 2374400500015 On the basis of Westcott's convention, thermal cross 2374400500016 section and resonance integral were deduced. 2374400500017 DECAY-DATA (96-CM-244,18.10YR,A,5804.,0.764, 2374400500018 A,5762.,0.236) 2374400500019 (95-AM-243,7367.YR,A,5275.,0.874, 2374400500020 A,5233.,0.110, 2374400500021 A,5181.,0.011) 2374400500022 ERR-ANALYS (ERR-T) Total uncertainty. 2374400500023 (ERR-1) Uncertainty due to Half-life of Am-243. 2374400500024 7367 +- 23 (yr) 2374400500025 (ERR-2) Uncertainty due to Half-life of Cm-244. 2374400500026 18.10 +- 0.02 (yr) 2374400500027 (ERR-3) Uncertainty due to irradiation time. 2374400500028 19595 +- 90 (sec) 2374400500029 STATUS (TABLE) Tables 11+12 in J.Nucl.Sci.Technol.58(2021)259.2374400500030 ENDBIB 28 0 2374400500031 COMMON 3 3 2374400500032 ERR-1 ERR-2 ERR-3 2374400500033 PER-CENT PER-CENT PER-CENT 2374400500034 0.31 0.11 0.46 2374400500035 ENDCOMMON 3 0 2374400500036 DATA 3 1 2374400500037 EN-MIN DATA ERR-T 2374400500038 EV B B 2374400500039 0.133 2300. 200. 2374400500040 ENDDATA 3 0 2374400500041 ENDSUBENT 40 0 2374400599999 SUBENT 23744006 20210906 23022374400600001 BIB 4 9 2374400600002 REACTION (95-AM-243(N,G)95-AM-244-M/G,,SIG/RAT) 2374400600003 ANALYSIS Calculated using thermal capture cross section to 2374400600004 Am-244g and Am-244m+g. 2374400600005 ERR-ANALYS (DATA-ERR) Total uncertainty 2374400600006 STATUS (TABLE) Table 14 of J.Nucl.Sci.Technol.58(2021)259. 2374400600007 (DEP,23744002) Thermal cross section to Am-244g: 2374400600008 4.73 +- 0.27 (b) 2374400600009 (DEP,23744004) Thermal cross section to Am-244m+g: 2374400600010 88.5 +- 4.0 (b) 2374400600011 ENDBIB 9 0 2374400600012 NOCOMMON 0 0 2374400600013 DATA 3 1 2374400600014 EN DATA DATA-ERR 2374400600015 EV NO-DIM NO-DIM 2374400600016 0.0253 17.7 1.3 2374400600017 ENDDATA 3 0 2374400600018 ENDSUBENT 17 0 2374400699999 ENDENTRY 6 0 2374499999999