ENTRY 32706 20120917 31573270600000001
SUBENT 32706001 20120917 31573270600100001
BIB 16 49 3270600100002
TITLE Measurements of the 71Ga(n,g)72m+gGa cross section in 3270600100003
the neutron energy range of 13.5 to 14.8 MeV 3270600100004
AUTHOR (Junhua Luo,Rong Liu,Li Jiang) 3270600100005
INSTITUTE (3CPRHXU) School of Physics and Electromechanical 3270600100006
Engineering 3270600100007
(3CPRNPC) 3270600100008
REFERENCE (J,NSE,172,122,2012) 3270600100009
FACILITY (NGEN,3CPRNPC) PD-300 neutron generator 3270600100010
SAMPLE (31-GA-71,NAT=0.398929) About 8 g of Ga2O3 powder of 3270600100011
natural isotopic composition (>99.99% pure) was 3270600100012
pressed at 10 ton/cm2, and a pellet, 0.4 cm thick and 3270600100013
2.0 cm in diameter was obtained. 3270600100014
DETECTOR (HPGE) A HPGe detector with a relative efficiency of 3270600100015
~68%, and an energy resolution of 1.69 keV at 1332 keV 3270600100016
for Co-60. 3270600100017
METHOD (ACTIV) Irradiation of the samples was carried out and 3270600100018
lasted 121 min with a yield around 3E10 to 4E10 3270600100019
n/(4pi*s). Cooled for 21 to 24 h after irradiation. 3270600100020
MONITOR (13-AL-27(N,A)11-NA-24,,SIG) 3270600100021
DECAY-MON (11-NA-24,14.959HR,DG,1368.6,1.00) 3270600100022
MONIT-REF (,M.Wagner+,B,PH-DAT,13-5,1990) 3270600100023
The cross section of monitor reaction was determined by3270600100024
interpolation of the evaluated values of the reference.3270600100025
INC-SOURCE (D-T) The tritium-titanium (T-Ti) target used in the 3270600100026
generator was 2.40 mg/cm2. The effective source 3270600100027
neutron energy at irradiation position was determined 3270600100028
by cross section ratios for the (n,2n) reaction of Nb 3270600100029
and Zr target. 3270600100030
ERR-ANALYS (ERR-T) Total uncertainty of measurement 3270600100031
(ERR-S,0.1,3.9) Counting statistics 3270600100032
(ERR-1,2.,3.) Detector efficiency 3270600100033
(ERR-2,0.1,1.) Uncertainties of irradiation, cooling 3270600100034
and measuring times 3270600100035
(ERR-3,0.,5.) Coincidence sum effect of cascade 3270600100036
gamma-rays 3270600100037
(ERR-4) Weight of sample 3270600100038
(ERR-5) Self-absorption of gamma-ray 3270600100039
(MONIT-ERR) Standard cross sections uncertainty 3270600100040
COMMENT Author did not do a vacant target experiment, but the 3270600100041
new T-Ti target was used in the present work, and the 3270600100042
time of irradiating the samples was short around 2 h. 3270600100043
Furthermore, the samples were wrapped in cadmium foil 3270600100044
and placed at the appropriate positions, which were 3270600100045
both far and also near around 3 to 5 cm away from the 3270600100046
center of the T-Ti target, so the influence of 3270600100047
low-energy neutrons was reduced to a very low level. 3270600100048
STATUS (TABLE) Table II of J,NSE,172,2012 3270600100049
HISTORY (20120917C)Compiled by Youxiang ZHUANG and Guochang 3270600100050
CHEN (CNDC) 3270600100051
ENDBIB 49 0 3270600100052
COMMON 3 3 3270600100053
EN-RSL ERR-4 ERR-5 3270600100054
MEV PER-CENT PER-CENT 3270600100055
0.2 0.1 0.5 3270600100056
ENDCOMMON 3 0 3270600100057
ENDSUBENT 56 0 3270600199999
SUBENT 32706002 20120917 31573270600200001
BIB 2 8 3270600200002
REACTION 1(31-GA-71(N,G)31-GA-72,,SIG) 3270600200003
2(31-GA-71(N,G)31-GA-72,,SIG) 3270600200004
3(31-GA-71(N,G)31-GA-72,,SIG) 3270600200005
4(31-GA-71(N,G)31-GA-72,,SIG) 3270600200006
DECAY-DATA1(31-GA-72-G,14.10HR,DG,834.01,0.960) 3270600200007
2(31-GA-72-G,14.10HR,DG,629.95,0.248) 3270600200008
3(31-GA-72-G,14.10HR,DG,894.26,0.0988) 3270600200009
4(31-GA-72-G,14.10HR,DG,1050.73,0.0691) 3270600200010
ENDBIB 8 0 3270600200011
NOCOMMON 0 0 3270600200012
DATA 11 3 3270600200013
EN DATA 1ERR-T 1DATA 2ERR-T 2DATA 33270600200014
ERR-T 3DATA 4ERR-T 4MONIT MONIT-ERR 3270600200015
MEV MB MB MB MB MB 3270600200016
MB MB MB MB MB 3270600200017
13.5 2.22 0.20 1.92 0.21 1.64 3270600200018
0.25 1.70 0.29 125.7 0.8 3270600200019
14.1 1.76 0.16 1.51 0.16 1.26 3270600200020
0.17 1.39 0.22 121.6 0.6 3270600200021
14.8 1.08 0.10 0.94 0.09 0.74 3270600200022
0.09 0.89 0.14 111.9 0.5 3270600200023
ENDDATA 10 0 3270600200024
ENDSUBENT 23 0 3270600299999
SUBENT 32706003 20120917 31573270600300001
BIB 3 5 3270600300002
REACTION (31-GA-71(N,G)31-GA-72,,SIG,,,DERIV) 3270600300003
ANALYSIS Weighted average of cross sections for 629.95, 834.01, 3270600300004
894.26 and 1050.73 keV gamma lines. 3270600300005
STATUS (DEP,32706002) Data from 629.95, 834.01, 894.26 and 3270600300006
1050.73 keV gammas 3270600300007
ENDBIB 5 0 3270600300008
NOCOMMON 0 0 3270600300009
DATA 5 3 3270600300010
EN DATA ERR-T MONIT MONIT-ERR 3270600300011
MEV MB MB MB MB 3270600300012
13.5 1.93 0.12 125.7 0.8 3270600300013
14.1 1.50 0.09 121.6 0.6 3270600300014
14.8 0.91 0.05 111.9 0.5 3270600300015
ENDDATA 5 0 3270600300016
ENDSUBENT 15 0 3270600399999
ENDENTRY 3 0 3270699999999