ENTRY 31599 20081229 31333159900000001 SUBENT 31599001 20081229 31333159900100001 BIB 15 45 3159900100002 TITLE Measurement of neutron capture cross sections of 3159900100003 139La, 152Sm and 191,193Ir at 55 and 144 keV 3159900100004 AUTHOR (V.H.Tan,T.T.Anh,N.C.Hai,P.N.Son,T.Fukahori) 3159900100005 INSTITUTE (3VN VN) Vietnam Atomic Energy Commission, 3159900100006 59-Ly Thuong Kiet, Hanoi 3159900100007 (3VN DAL) 3159900100008 (2JPNJAE) Nuclear Data Center, Nuclear Science and 3159900100009 Engineering Directorate 3159900100010 REFERENCE (S,JAEA-C-2008-006,40,2008) 3159900100011 FACILITY (REAC,3VN DAL) Dalat Nuclear Research Insitute 3159900100012 INC-SOURCE (REAC) Flux density 3159900100013 5.61x10**5 n/cm2/s (En= 55 keV) 3159900100014 2.14x10**6 n/cm2/s (En= 144 keV) 3159900100015 SAMPLE Chemical form: La2O3, Sm2O3 and IrO2 3159900100016 (99.99% purity, natural oxide powders) 3159900100017 Each sample was sandwiched between two gold disks, 3159900100018 and the sample groups were wrapped in Cd covers with 3159900100019 0.5mm in thickness with aim to reject most of thermal 3159900100020 neutron background. 3159900100021 METHOD (ACTIV) Irradiated for 70 hours 3159900100022 (FNB) Filter 3159900100023 98cm Si +35g/cm2 S + 0.2g/cm2 10B (En= 55 keV) 3159900100024 98cm Si +1cm Ti + 0.2g/cm2 10B (En= 144 keV) 3159900100025 DETECTOR (HPGE) The activities of samples and gold foils were 3159900100026 measured with the high resolution and 3159900100027 efficiency calibrated HPGe detector, and the 3159900100028 samples were placed on the surface of the 3159900100029 detector because of their weak activities. 3159900100030 MONITOR ((MONIT)79-AU-197(N,G)79-AU-198,,SIG) 3159900100031 The standard gold foils with 2.54cm in diameter and 3159900100032 0.01mm in thick were used as the neutron flux monitors 3159900100033 MONIT-REF (,P.G.Young+,3,ENDF/B-VI.8,7925,2001) 3159900100034 DECAY-MON (79-AU-198,2.6952D,DG,411.8,0.956) 3159900100035 ERR-ANALYS (ERR-T) The experimental uncertainties are 5 to 10%, 3159900100036 which are mainly due to: 3159900100037 - the statistical errors (0.1-2%) 3159900100038 (ERR-1) - gamma-ray detection efficiency (3.5%) 3159900100039 (ERR-2) - reference cross section value (3.0%) 3159900100040 (ERR-3) - correction for neutron resonance 3159900100041 capture, self-shielding and 3159900100042 multiscattering effects (~3%) 3159900100043 STATUS (TABLE) Data from the reference 3159900100044 HISTORY (20070727C) SD 3159900100045 (20080209A) SD: add laboratory to facility 3159900100046 (20081229A) On. BIB section updated 3159900100047 ENDBIB 45 0 3159900100048 COMMON 3 3 3159900100049 ERR-1 ERR-2 ERR-3 3159900100050 PER-CENT PER-CENT PER-CENT 3159900100051 3.5 3.0 3. 3159900100052 ENDCOMMON 3 0 3159900100053 ENDSUBENT 52 0 3159900199999 SUBENT 31599002 20070727 31233159900200001 BIB 2 2 3159900200002 REACTION (57-LA-139(N,G)57-LA-140,,SIG) 3159900200003 DECAY-DATA (57-LA-140,1.6781D,DG,487.02,0.455) 3159900200004 ENDBIB 2 0 3159900200005 NOCOMMON 0 0 3159900200006 DATA 5 2 3159900200007 EN EN-RSL-FW DATA ERR-T MONIT 3159900200008 KEV KEV MB MB MB 3159900200009 55. 8. 22.4 1.2 414.61 3159900200010 144. 22. 12.01 0.58 277.21 3159900200011 ENDDATA 4 0 3159900200012 ENDSUBENT 11 0 3159900299999 SUBENT 31599003 20070727 31233159900300001 BIB 2 2 3159900300002 REACTION (62-SM-152(N,G)62-SM-153,,SIG) 3159900300003 DECAY-DATA (62-SM-153,46.50HR,DG,103.2,0.293) 3159900300004 ENDBIB 2 0 3159900300005 NOCOMMON 0 0 3159900300006 DATA 5 2 3159900300007 EN EN-RSL-FW DATA ERR-T MONIT 3159900300008 KEV KEV MB MB MB 3159900300009 55. 8. 345.5 19.4 414.61 3159900300010 144. 22. 258.7 14.5 277.21 3159900300011 ENDDATA 4 0 3159900300012 ENDSUBENT 11 0 3159900399999 SUBENT 31599004 20070727 31233159900400001 BIB 2 2 3159900400002 REACTION (77-IR-191(N,G)77-IR-192,,SIG) 3159900400003 DECAY-DATA (77-IR-192,73.827D,DG,316.5,0.827) 3159900400004 ENDBIB 2 0 3159900400005 NOCOMMON 0 0 3159900400006 DATA 5 2 3159900400007 EN EN-RSL-FW DATA ERR-T MONIT 3159900400008 KEV KEV MB MB MB 3159900400009 55. 8. 1016.5 57.2 414.61 3159900400010 144. 22. 514. 29.4 277.21 3159900400011 ENDDATA 4 0 3159900400012 ENDSUBENT 11 0 3159900499999 SUBENT 31599005 20070727 31233159900500001 BIB 2 2 3159900500002 REACTION (77-IR-193(N,G)77-IR-194,,SIG) 3159900500003 DECAY-DATA (77-IR-194,19.28HR,DG,328.45,0.131) 3159900500004 ENDBIB 2 0 3159900500005 NOCOMMON 0 0 3159900500006 DATA 5 2 3159900500007 EN EN-RSL-FW DATA ERR-T MONIT 3159900500008 KEV KEV MB MB MB 3159900500009 55. 8. 566.7 32.6 414.61 3159900500010 144. 22. 404.5 22.8 277.21 3159900500011 ENDDATA 4 0 3159900500012 ENDSUBENT 11 0 3159900599999 ENDENTRY 5 0 3159999999999