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