ENTRY 31647 20081128 31313164700000001 SUBENT 31647001 20081128 31313164700100001 BIB 15 60 3164700100002 TITLE Thermal neutron capture cross sections for the 3164700100003 152Sm(n,gamma)153Sm and 154Sm(n,gamma)155Sm 3164700100004 reactions at 0.0536 eV energy 3164700100005 AUTHOR (M.S.Uddin,M.H.Chowdhury,S.M.Hossain,Sk.A.Latif, 3164700100006 M.A.Islam,M.A.Hafiz,S.H.Mubin,A.K.M.Zakaria, 3164700100007 S.M.Yunus,S.M.Azharul Islam) 3164700100008 INSTITUTE (3BANSAV,3BANDAC) 3164700100009 Institute of Nuclear Science and Technology, 3164700100010 Atomic Energy Research Establishment, Savar, 3164700100011 GPO Box No.3787, Dhaka-1000, Bangladesh 3164700100012 REFERENCE (J,NIM/B,266,4855,2008) 3164700100013 FACILITY (REAC,3BANSAV) TRIGA Mark-II research reactor 3164700100014 INC-SOURCE (REAC) a monoenergetic (0.0536 eV) collimated (1.6 x 3164700100015 5 cm2) neutron beam of 1.85 x 10**5 n/cm2/s for 2 3164700100016 hrs at the outer end position of the last collimator. 3164700100017 SAMPLE The Sm2O3 powder was pressed with a pressure of 5 tons 3164700100018 per cm2 using a hydraulic press to prepare a pellet of 3164700100019 0.82 g with a diameter of 1.2 cm and thickness 0.16 cm.3164700100020 The pellet was sandwiched with two pure gold foils 3164700100021 (25 mu-m thick and 8 mm diameter) for irradiation. 3164700100022 Two gold foils of approximately same size and weight 3164700100023 were attached at the front and back of the pellet to 3164700100024 determine the neutron beam attenuation along the target3164700100025 The isotopes and their natural occurrences are 3164700100026 144Sm (3.1%), 147Sm (15%), 148Sm (11%), 149Sm (14%), 3164700100027 150Sm (7.4%), 152Sm (27%) and 154Sm (23%). 3164700100028 DETECTOR (HPGE) using high-purity germanium (HPGe) gamma-ray 3164700100029 spectroscopy (Canberra, 15% relative efficiency, 3164700100030 1.8 keV resolution at 1332.5 keV of 60Co) coupled 3164700100031 with a digital gamma spectrometry system and Maestro 3164700100032 data acquisition software. 3164700100033 METHOD (EXTB,GSPEC) 3164700100034 MONITOR (79-AU-197(N,G)79-AU-198,,SIG) Value for monitor was 3164700100035 evaluated from the trend line of experimental data 3164700100036 reported by Yamamoto, Pavlenko, Haddad and evaluated 3164700100037 cross sections reported in the ENDF/B-VII and 3164700100038 JENDL-3.3 libraries (see MONIT-REF). 3164700100039 DECAY-MON (79-AU-198,2.695D,DG,411.8,0.955) 3164700100040 MONIT-REF (22370001,S.Yamamoto+,J,NST,33,815,1996) 3164700100041 (40464002,E.A.Pavlenko+,C,75KIEV,3,171,1975) 3164700100042 (12196003,E.Haddad+,J,NIM,31,125,1964) 3164700100043 also: 3164700100044 ENDF/B-VII http://www.nndc.bnl.gov/exfor7/endf00.htm 3164700100045 and JENDL-3.3 Japan Atomic Energy Research Institute. 3164700100046 Nuclear Data Center. Copyright, 2002 JAERI. 3164700100047 ERR-ANALYS (ERR-T) Total uncertainties include: 3164700100048 * Statistical uncertainty 1-5% in case of 153Sm or 3164700100049 1-3% in case of 155Sm 3164700100050 (ERR-1) uncertainty in gamma detection efficiency 3164700100051 * uncertainty in sample mass - 0.01% 3164700100052 * uncertainty in self-shielding factor - 0.01% 3164700100053 (ERR-2) uncertainty in neutrn flux 3164700100054 (ERR-3) uncertainty in definiton of half-life 3164700100055 * and uncertainty in decay branching ratio - 1.9% in 3164700100056 case of 155Sm 3164700100057 STATUS (TABLE) tbl. from ref. 3164700100058 (APRVD) Entry approved by Dr.M.S.Uddin 3164700100059 HISTORY (20080823C) SD 3164700100060 (20081030A) SD. Ref. on publication added. 3164700100061 Article published in NIM/b. 3164700100062 ENDBIB 60 0 3164700100063 COMMON 6 3 3164700100064 EN EN-ERR MONIT MONIT-ERR ERR-1 ERR-2 3164700100065 EV EV B B PER-CENT PER-CENT 3164700100066 0.0536 0.00026 68.5 1.7 3.0 3.5 3164700100067 ENDCOMMON 3 0 3164700100068 ENDSUBENT 67 0 3164700199999 SUBENT 31647002 20080823 31303164700200001 BIB 2 2 3164700200002 REACTION (62-SM-152(N,G)62-SM-153,,SIG) 3164700200003 DECAY-DATA (62-SM-153,46.5HR,DG,103.17,0.283) 3164700200004 ENDBIB 2 0 3164700200005 COMMON 1 3 3164700200006 ERR-3 3164700200007 PER-CENT 3164700200008 0.21 3164700200009 ENDCOMMON 3 0 3164700200010 DATA 2 1 3164700200011 DATA ERR-T 3164700200012 B B 3164700200013 144.6 8.6 3164700200014 ENDDATA 3 0 3164700200015 ENDSUBENT 14 0 3164700299999 SUBENT 31647003 20080823 31303164700300001 BIB 3 3 3164700300002 REACTION (62-SM-154(N,G)62-SM-155,,SIG) 3164700300003 DECAY-DATA (62-SM-155,22.2MIN,DG,104.32,0.73) 3164700300004 ERR-ANALYS (ERR-4) Decay branching ratio - 1.9 3164700300005 ENDBIB 3 0 3164700300006 COMMON 2 3 3164700300007 ERR-3 ERR-4 3164700300008 PER-CENT PER-CENT 3164700300009 0.2 1.9 3164700300010 ENDCOMMON 3 0 3164700300011 DATA 2 1 3164700300012 DATA ERR-T 3164700300013 B B 3164700300014 5.9 0.29 3164700300015 ENDDATA 3 0 3164700300016 ENDSUBENT 15 0 3164700399999 ENDENTRY 3 0 3164799999999