ENTRY 32704 20120821 31573270400000001 SUBENT 32704001 20120821 31573270400100001 BIB 16 52 3270400100002 TITLE Cross section measurements for gallium in the neutron 3270400100003 energy range of 13.5 to 14.8 MeV 3270400100004 AUTHOR (J.Luo,R.Liu,L.Jiang) 3270400100005 INSTITUTE (3CPRHXU) School of Physics and Electromechanical 3270400100006 Engineering 3270400100007 (3CPRNPC) 3270400100008 REFERENCE (J,RCA,100,(4),231,2012) 3270400100009 FACILITY (NGEN,3CPRNPC) Pd-300 neutron generator 3270400100010 SAMPLE About 8 gram Ga2O3 powder of natural isotope 3270400100011 composition sample (>99.99% purity) was pressed at 10 3270400100012 ton/cm2, and a pellet, 0.4 cm thick and 2.0 cm in 3270400100013 diameter was obtained. Monitor foils of Al (99.999% 3270400100014 pure, 0.04 mm thick) of the same diameter as the 3270400100015 pellets were then attached in front and at the back of 3270400100016 each sample. Finally, wrapped in 1 mm thick cadmium 3270400100017 foil. 3270400100018 DETECTOR (HPGE) The crystal geometry is 70.1 x 72.3 mm in 3270400100019 diameter and length. The relative efficiency is about 3270400100020 68%, and energy resolution is 1.69 keV at 1332 keV 3270400100021 gamma ray from Co-60. The efficiency of the detector 3270400100022 was pre-calibrated using various standard gamma 3270400100023 sources such as Mn-54, Co-57, Co-60, Cd-119, Ba-133, 3270400100024 Cs-137, Eu-152, Am-241 and Ra-226. 3270400100025 METHOD (ACTIV) Irradiation of the samples was lasted 121 min 3270400100026 with a yield around 3E10 to 4E10 n/s. 3270400100027 MONITOR (13-AL-27(N,A)11-NA-24,,SIG) 3270400100028 DECAY-MON (11-NA-24,14.959HR,DG,1368.6,1.00) 3270400100029 MONIT-REF (,M.Wagner+,B,PH-DAT,13-5,1990) The cross section of 3270400100030 monitor reaction was determined by interpolation of the3270400100031 evaluated values of the reference. 3270400100032 INC-SOURCE (D-T) An effective deuteron beam energy of 125 keV 3270400100033 and beam current of 200 uA were used to produce 3270400100034 neutrons. And the tritium-titanium (T-Ti) target used 3270400100035 in the generator was 2.40 mg/cm2 thick. 3270400100036 ERR-ANALYS (ERR-T) Total uncertainty of cross section is in the 3270400100037 range from 10% to 20%. The uncertainties resulted from 3270400100038 counting statistics, standard cross sections 3270400100039 uncertainties, detector efficiency, weight of samples, 3270400100040 self-absorption of gamma-rays and the coincidence sum 3270400100041 effect of cascade gamma-rays. 3270400100042 CORRECTION The neutron flux was monitored by a uranium fission 3270400100043 chamber so that corrections were made for small 3270400100044 variations in the yield. The self-absorption of the 3270400100045 sample at a given gamma-energy, the coincidence sum 3270400100046 effect of cascade gamma-rays in the investigated 3270400100047 nuclide and in the counting geometry were taken into 3270400100048 account in data analysis, respectively. 3270400100049 STATUS (TABLE) All measured reactions data and monitor 3270400100050 reaction data are taken from Table 2 at page 233 in 3270400100051 J,RCA,100,231,2012. 3270400100052 HISTORY (20120821C) Compiled by Youxiang ZHUANG and Guochang 3270400100053 CHEN (CNDC) 3270400100054 ENDBIB 52 0 3270400100055 NOCOMMON 0 0 3270400100056 ENDSUBENT 55 0 3270400199999 SUBENT 32704002 20120821 31573270400200001 BIB 3 5 3270400200002 REACTION 1(31-GA-69(N,2N)31-GA-68,,SIG) 3270400200003 2(31-GA-69(N,P)30-ZN-69-M,,SIG) 3270400200004 DECAY-DATA1(31-GA-68,67.629MIN,DG,1077.35,0.030) 3270400200005 2(30-ZN-69-M,13.76HR,DG,438.634,0.9477) 3270400200006 SAMPLE (31-GA-69,NAT=0.60108) 3270400200007 ENDBIB 5 0 3270400200008 NOCOMMON 0 0 3270400200009 DATA 8 3 3270400200010 EN EN-ERR DATA 1ERR-T 1DATA 2ERR-T 23270400200011 MONIT MONIT-ERR 3270400200012 MEV MEV MB MB MB MB 3270400200013 MB MB 3270400200014 13.5 0.2 838. 93. 16.9 2.7 3270400200015 125.7 0.8 3270400200016 14.1 0.2 887. 96. 18.2 2.7 3270400200017 121.6 0.6 3270400200018 14.8 0.2 933. 90. 21.5 3.3 3270400200019 111.9 0.5 3270400200020 ENDDATA 10 0 3270400200021 ENDSUBENT 20 0 3270400299999 SUBENT 32704003 20120821 31573270400300001 BIB 3 7 3270400300002 REACTION 1(31-GA-71(N,2N)31-GA-70,,SIG) 3270400300003 2(31-GA-71(N,P)30-ZN-71-M,,SIG) 3270400300004 3(31-GA-71(N,N+A)29-CU-67,,SIG) 3270400300005 DECAY-DATA1(31-GA-70,21.14MIN,DG,1039.2,0.0065) 3270400300006 2(30-ZN-71-M,3.96HR,DG,386.28,0.930) 3270400300007 3(29-CU-67,61.83HR,DG,184.577,0.487) 3270400300008 SAMPLE (31-GA-71,NAT=0.39892) 3270400300009 ENDBIB 7 0 3270400300010 NOCOMMON 0 0 3270400300011 DATA 10 3 3270400300012 EN EN-ERR DATA 1ERR-T 1DATA 2ERR-T 23270400300013 DATA 3ERR-T 3MONIT MONIT-ERR 3270400300014 MEV MEV MB MB MB MB 3270400300015 MB MB MB MB 3270400300016 13.5 0.2 950. 159. 8.4 1.2 3270400300017 1.5 0.3 125.7 0.8 3270400300018 14.1 0.2 1030. 147. 10.1 2.1 3270400300019 2.6 0.6 121.6 0.6 3270400300020 14.8 0.2 1080. 180. 10.6 1.8 3270400300021 3.6 0.6 111.9 0.5 3270400300022 ENDDATA 10 0 3270400300023 ENDSUBENT 22 0 3270400399999 ENDENTRY 3 0 3270499999999