ENTRY 32761 20181119 31873276100000001 SUBENT 32761001 20181119 31873276100100001 BIB 15 47 3276100100002 TITLE Cross section measurements for 199Hg(n,p)199Au, 3276100100003 198Hg(n,p)198Au, 196Hg(n,p)196Au and 196Hg(n,d+np+pn) 3276100100004 195Au reactions 3276100100005 AUTHOR (Yuan Junqian, Kong Xiangzhong, Yang Jingkang, 3276100100006 Wang Huaiyi) 3276100100007 INSTITUTE (3CPRLNZ,3CPRNIX) 3276100100008 REFERENCE ((J,CNDP,13,16,1995)=(R,INDC(CPR)-34,16,1995)) 3276100100009 FACILITY (NGEN,3CPRLNZ) ZF-300-II intense neutron generator 3276100100010 INC-SOURCE (D-T) Deuteron beam was 125 keV effective energy and 3276100100011 20 mA current. The thickness of T-Ti target was about 3276100100012 0.9 mg/cm2. The neutron flux fluctuation was 3276100100013 monitored by a uranium fission chamber. 3276100100014 SAMPLE Natural oxide mercury powder was pressed in to disc 3276100100015 of 20 mm diameter and packed in a thin polyethylene 3276100100016 foil. Each sample was sandwiched between two iron 3276100100017 foils, which used to measure the neutron fluence on 3276100100018 the sample. 5 groups of samples were placed 3276100100019 respectively at 5 angles distances ranging from 0 3276100100020 deg to 120 deg relative to the beam direction and 3276100100021 distances of samples from the target were about 5 to 3276100100022 25 cm. 3276100100023 METHOD The irradiation lasted up to 61 hours with neutron 3276100100024 intensity of about 1-3E12 n/s/4pi. 3276100100025 DETECTOR (HPGE) The activities of the samples and monitors 3276100100026 were measured by gamma ray spectroscopy using a 3276100100027 CH8403 coaxial HPGe detector made in China in 3276100100028 conjunction with a EG and ORTEC 7450 Multichannel 3276100100029 Analyzer. The energy resolution of the detector is 3276100100030 2.7 keV for 1.33 MeV gamma ray. 3276100100031 MONITOR (26-FE-54(N,P)25-MN-54,,SIG) The abundance of 54Fe 3276100100032 was 0.0058 3276100100033 DECAY-MON (25-MN-54,312.2D,DG,834.8,0.9997) 3276100100034 CORRECTION Corrections could be made for variance of neutron 3276100100035 yield during the irradiation. Some corrections were 3276100100036 made for the effects of neutron intensity fluctuation, 3276100100037 gamma ray self-absorption in the sample, the sum 3276100100038 peak effects in the investigated nuclide and the 3276100100039 counting geometry. 3276100100040 ERR-ANALYS (ERR-T) The errors were from counting statistics, 3276100100041 standard cross sections, detector efficiency, 3276100100042 weighting of samples, self-absorption of gamma-gay, 3276100100043 coincidence sum effect of cascade gamma-rays. 3276100100044 (ERR-1) The error of the relative photopeak detection 3276100100045 efficiency of the detector was 2%. 3276100100046 STATUS (TABLE) Data were obtained from TABLE 2 of 3276100100047 Comm.Nucl.Data Prog,13,16,1995 3276100100048 HISTORY (20181119C) Compiled by Tao Xi(CNDC) 3276100100049 ENDBIB 47 0 3276100100050 COMMON 1 3 3276100100051 ERR-1 3276100100052 PER-CENT 3276100100053 2. 3276100100054 ENDCOMMON 3 0 3276100100055 ENDSUBENT 54 0 3276100199999 SUBENT 32761002 20181119 31873276100200001 BIB 3 4 3276100200002 REACTION ((80-HG-199(N,P)79-AU-199,,SIG)+ 3276100200003 (80-HG-200(N,X)79-AU-199,,SIG,,RAB)) 3276100200004 DECAY-DATA (79-AU-199,3.139D,DG,208.0,0.0876) 3276100200005 SAMPLE (80-HG-199,NAT=0.1684) 3276100200006 ENDBIB 4 0 3276100200007 NOCOMMON 0 0 3276100200008 DATA 3 3 3276100200009 EN DATA ERR-T 3276100200010 MEV MB MB 3276100200011 14.5 2.4 0.5 3276100200012 14.7 2.6 0.3 3276100200013 14.8 2.7 0.1 3276100200014 ENDDATA 5 0 3276100200015 ENDSUBENT 14 0 3276100299999 SUBENT 32761003 20181119 31873276100300001 BIB 3 4 3276100300002 REACTION ((80-HG-198(N,P)79-AU-198,,SIG)+ 3276100300003 (80-HG-199(N,X)79-AU-198,,SIG,,RAB)) 3276100300004 DECAY-DATA (79-AU-198-G,2.7D,DG,411.8,0.955) 3276100300005 SAMPLE (80-HG-198,NAT=0.1002) 3276100300006 ENDBIB 4 0 3276100300007 NOCOMMON 0 0 3276100300008 DATA 3 4 3276100300009 EN DATA ERR-T 3276100300010 MEV MB MB 3276100300011 14.1 3.1 0.2 3276100300012 14.5 5.7 0.3 3276100300013 14.7 5.9 0.3 3276100300014 14.8 5.6 0.3 3276100300015 ENDDATA 6 0 3276100300016 ENDSUBENT 15 0 3276100399999 SUBENT 32761004 20181119 31873276100400001 BIB 3 3 3276100400002 REACTION (80-HG-196(N,P)79-AU-196,,SIG) 3276100400003 DECAY-DATA (79-AU-196-G,6.18D,DG,355.7,0.88) 3276100400004 SAMPLE (80-HG-196,NAT=0.00146) 3276100400005 ENDBIB 3 0 3276100400006 NOCOMMON 0 0 3276100400007 DATA 3 4 3276100400008 EN DATA ERR-T 3276100400009 MEV MB MB 3276100400010 14.1 6.2 0.7 3276100400011 14.5 5.2 0.5 3276100400012 14.7 13.3 1.1 3276100400013 14.8 18.0 1.0 3276100400014 ENDDATA 6 0 3276100400015 ENDSUBENT 14 0 3276100499999 SUBENT 32761005 20181119 31873276100500001 BIB 3 3 3276100500002 REACTION (80-HG-196(N,X)79-AU-195,,SIG) 3276100500003 DECAY-DATA (79-AU-195-G,186.0D,DG,98.86,0.109) 3276100500004 SAMPLE (80-HG-196,NAT=0.00146) 3276100500005 ENDBIB 3 0 3276100500006 NOCOMMON 0 0 3276100500007 DATA 3 5 3276100500008 EN DATA ERR-T 3276100500009 MEV MB MB 3276100500010 13.8 633. 92. 3276100500011 14.1 664. 67. 3276100500012 14.5 726. 82. 3276100500013 14.7 577. 37. 3276100500014 14.8 604. 32. 3276100500015 ENDDATA 7 0 3276100500016 ENDSUBENT 15 0 3276100599999 ENDENTRY 5 0 3276199999999