ENTRY 32712 20140523 31643271200000001 SUBENT 32712001 20140523 31643271200100001 BIB 15 50 3271200100002 TITLE Cross-sections of Sc-45(n,2n)Sc-44m,g reaction from 3271200100003 the reaction threshold to 20 MeV 3271200100004 AUTHOR (J.Luo,R.Liu,L.Jiang,Z.Liu,G.Sun,S.Ge) 3271200100005 INSTITUTE (3CPRHXU,3CPRBJG,3CPRNPC) 3271200100006 REFERENCE (J,RCA,101,607,2013) 3271200100007 #doi:10.1524/ract.2013.2065 3271200100008 FACILITY (NGEN,3CPRNPC) Pd-300 neutron generator 3271200100009 SAMPLE About 7 gram of high purity Sc2O3 powder(natural 3271200100010 isotopic composition) was pressed at 10 ton/cm2, and 3271200100011 a pellet, 0.4 cm thick and 2.0 cm in diameter was 3271200100012 obtained. Monitor foils (Nb, 99.99% pure, 0.5 mm 3271200100013 thick) of the same diameter as the pellets were then 3271200100014 attached in front and at the back of each sample. 3271200100015 DETECTOR (HPGE) The crystal geometry is 70.1 x 72.3 mm in 3271200100016 diameter and length. The relative efficiency is about 3271200100017 68%, and energy resolution is 1.69 keV at 1332 keV 3271200100018 gamma ray from Co-60. The efficiency of the detector 3271200100019 was pre-calibrated using various standard gamma 3271200100020 sources, which were Mn-54, Co-57, Co-60, Cd-109, 3271200100021 Ba-133, Cs-137, Eu-152, Am-241 and Ra-226. 3271200100022 (FISCH) The neutron flux was monitored by a uranium 3271200100023 fission chamber. 3271200100024 METHOD (ACTIV) Irradiation of the samples was lasted about 2 3271200100025 hours with a yield around 3E10 to 4E10 n/s. The groups 3271200100026 of samples were placed at 0deg., 90deg. or 135deg. 3271200100027 angles relative to the beam direction and centered 3271200100028 about the T-Ti target at distances of around 5 cm. 3271200100029 MONITOR (41-NB-93(N,2N)41-NB-92-M,,SIG) 3271200100030 MONIT-REF (,M.Wagner+,B,PH-DAT,13-5,1990) 3271200100031 INC-SOURCE (D-T) An effective deuteron beam energy of 125 keV 3271200100032 and beam current of 200 uA were used to produce 3271200100033 neutrons. The tritium-titanium (T-Ti) target used in 3271200100034 the generator was 2.38 mg/cm2 thick. 3271200100035 ERR-ANALYS (ERR-T) Total uncertainty of cross section 3271200100036 (ERR-S,0.1,1.0) Counting statistics (0.1-1.0%) 3271200100037 (ERR-1,2.,3.) Detector efficiency (2-3%) 3271200100038 (ERR-2) Weight of samples (0.1%) 3271200100039 (ERR-3) Self-absorption of gamma-ray (0.5%) 3271200100040 (ERR-4,0.,5.) The coincidence sum effect of cascade 3271200100041 gamma-rays (0-5%) 3271200100042 (ERR-5,0.1,1.) The uncertainties of irradiation, 3271200100043 cooling and measuring times (0.1-1.%) 3271200100044 (MONIT-ERR) Standard cross sections (1.5%) 3271200100045 CORRECTION Measurements were corrected for gamma-ray attenuations 3271200100046 and fluctuation of neutron flux. 3271200100047 STATUS (TABLE) All measured reactions cross sections are 3271200100048 taken from Table 2 at page 609 in J,RCA,101,607,2013, 3271200100049 and the isomeric cross section ratios are taken from 3271200100050 subsection 4.4 at page 610 in J,RCA,101,607,2013. 3271200100051 HISTORY (20140523C) Compiled by CHEN Guochang (CNDC) 3271200100052 ENDBIB 50 0 3271200100053 COMMON 3 3 3271200100054 ERR-2 ERR-3 MONIT-ERR 3271200100055 PER-CENT PER-CENT PER-CENT 3271200100056 0.1 0.5 1.5 3271200100057 ENDCOMMON 3 0 3271200100058 ENDSUBENT 57 0 3271200199999 SUBENT 32712002 20140523 31643271200200001 BIB 2 6 3271200200002 REACTION 1(21-SC-45(N,2N)21-SC-44-M,,SIG) 3271200200003 2(21-SC-45(N,2N)21-SC-44-G,,SIG) 3271200200004 3(21-SC-45(N,2N)21-SC-44,,SIG) 3271200200005 4(21-SC-45(N,2N)21-SC-44-M/G,,SIG/RAT) 3271200200006 DECAY-DATA1(21-SC-44-M,58.6HR,DG,271.13,0.867) 3271200200007 2(21-SC-44-G,3.927HR,DG,1157.03,0.999) 3271200200008 ENDBIB 6 0 3271200200009 NOCOMMON 0 0 3271200200010 DATA 10 3 3271200200011 EN EN-ERR DATA 1ERR-T 1DATA 2ERR-T 23271200200012 DATA 3ERR-T 3DATA 4ERR-T 4 3271200200013 MEV MEV MB MB MB MB 3271200200014 MB MB NO-DIM NO-DIM 3271200200015 13.5 0.2 76. 5. 98. 10.3271200200016 174. 15. 0.78 0.09 3271200200017 14.1 0.2 108. 7. 145. 13.3271200200018 253. 20. 0.74 0.08 3271200200019 14.8 0.2 134. 8. 186. 16.3271200200020 320. 24. 0.72 0.08 3271200200021 ENDDATA 10 0 3271200200022 ENDSUBENT 21 0 3271200299999 ENDENTRY 2 0 3271299999999