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