ENTRY 31635 20080801 31293163500000001
SUBENT 31635001 20080801 31293163500100001
BIB 14 59 3163500100002
TITLE Neutron capture cross-section measurement for the 3163500100003
186W(n,gamma) 187W reaction at 0.0536 eV energy 3163500100004
AUTHOR (M.S.Uddin,M.H.Chowdhury,S.M.Hossain,Sk.A.Latif, 3163500100005
M.A.Hafiz,M.A.Islam ,A.K.M.Zakaria,S.M.Azharul Islam) 3163500100006
INSTITUTE (3BANSAV) 3163500100007
Institute of Nuclear Science and Technology, Atomic 3163500100008
Energy Research Establishment, GPO Box No 3787, 3163500100009
Dhaka-1000, Bangladesh 3163500100010
(3BANBAN) Department of Physics, Jahangirnagar 3163500100011
University, Savar, Dhaka, Bangladesh; 3163500100012
Department of Physics, Comilla Victoria Government 3163500100013
College, Comilla, Bangladesh 3163500100014
REFERENCE (J,ARI,66,1235,2008) 3163500100015
FACILITY (REAC,3BANSAV) 3 MW TRIGA Mark-II research reactor 3163500100016
INC-SOURCE The neutron flux was determined individually for 3163500100017
both of two Au-foils irradiated at the front and 3163500100018
back of W-foil, and the obtained values are 1.423 x 3163500100019
10**5 and 1.408 x 10**5 n/cm2/s, respectively. 3163500100020
SAMPLE A foil of tungsten (1.2 cm diam. x 200mu-m thick; 3163500100021
purity 99.99%) of natural isotopic composition: 3163500100022
180W(0.127 0.01%), 182W(26.507 0.16%), 183W(14.317 3163500100023
0.04%) 184W(30.647 0.02%), and 186W(28.427 0.19%) and 3163500100024
thin goldfoils (1.2cm diam. x 25mmu-m thick; purity 3163500100025
99.99%) Two gold foils of approximately same size and 3163500100026
weight were attached at the front and back of the 3163500100027
tungsten foil, respectively to check the difference in 3163500100028
neutron beam intensity between entrance and exit of the3163500100029
target.To follow the effect of epithermal neutrons and 3163500100030
fastneutrons, the cadmium-covered gold foil and bare 3163500100031
aluminum foil were also irradiated. 3163500100032
DETECTOR (HPGE) The high-purity germanium (HPGe) gamma-ray 3163500100033
spectroscopy (Canberra, 15% relative efficiency, 3163500100034
1.8 keV resolution at 1332.5 keV of 60Co) coupled with 3163500100035
digital gamma spectrometry system and Maestro data 3163500100036
acquisition software. 3163500100037
MONITOR (79-AU-197(N,G)79-AU-198,,SIG) The neutron beam 3163500100038
intensity was determined from the measured activities 3163500100039
induced in gold monitor foils using the 3163500100040
197Au(n,gamma)198Au monitor reaction. The monitor 3163500100041
foils were measured with the same detector and in a 3163500100042
comparable geometry as the gallium oxide target. 3163500100043
DECAY-MON (79-AU-198,2.695D,DG,411.8,0.955) 3163500100044
MONIT-REF The cross-section of the monitor reaction was evaluated3163500100045
from the trend line of experimental data reported by 3163500100046
(22370001,Yamamoto+,J,NST,33,815,1996) 3163500100047
(40464001,Pavlenko+,C,75KIEV,3,171,197506) 3163500100048
(12196001,Haddad+,J,NIM,31,125,1964) 3163500100049
ERR-ANALYS (ERR-T) The total uncertainty includes: 3163500100050
* Statistical uncertainty of gamma-Ray counting 1-2% 3163500100051
* Sample mass 0.01 3163500100052
* Isotopic abundance 0.19 3163500100053
* Half-life 0.06 3163500100054
(ERR-1) uncertainty in cross section of the monitor 3163500100055
reaction 3163500100056
(ERR-2) uncertainty in efficiency calibration 3163500100057
(ERR-3) uncertainty in the decay branching ratio 3163500100058
STATUS (TABLE) tbl. 3 3163500100059
(APRVD) Entry was approved by Dr. Md. Shuza Uddin 3163500100060
HISTORY (20080731C) SD 3163500100061
ENDBIB 59 0 3163500100062
COMMON 5 3 3163500100063
EN EN-ERR ERR-1 ERR-2 ERR-3 3163500100064
EV EV PER-CENT PER-CENT PER-CENT 3163500100065
0.0536 0.00026 2.5 3.0 3.0 3163500100066
ENDCOMMON 3 0 3163500100067
ENDSUBENT 66 0 3163500199999
SUBENT 31635002 20080731 31293163500200001
BIB 2 2 3163500200002
REACTION (74-W-186(N,G)74-W-187,,SIG) 3163500200003
DECAY-DATA (74-W-187,23.72HR,DG,479.55,0.00022,DG,685.73,0.0004) 3163500200004
ENDBIB 2 0 3163500200005
NOCOMMON 0 0 3163500200006
DATA 4 1 3163500200007
DATA ERR-T MONIT MONIT-ERR 3163500200008
B B B B 3163500200009
26.6 1.6 68.5 1.7 3163500200010
ENDDATA 3 0 3163500200011
ENDSUBENT 10 0 3163500299999
ENDENTRY 2 0 3163599999999