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