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