ENTRY 32691 20120209 31543269100000001 SUBENT 32691001 20120209 31543269100100001 BIB 16 70 3269100100002 TITLE Cross-sections for formation of 178m2Hf and 179m2Hf 3269100100003 through reactions on natural hafnium at neutron 3269100100004 energy 14.8 +- 0.2 MeV 3269100100005 AUTHOR (Junhua Luo,Fei Tuo,Xiangzhong Kong) 3269100100006 INSTITUTE (3CPRHXU) School of Physics and Electromechanical 3269100100007 Engineering, Hexi University (Zhangye city, Gansu 3269100100008 Province) 3269100100009 (3CPRLNZ) School of Nuclear Science and Technology, 3269100100010 Lanzhou University 3269100100011 (3CPRCPR) National Institute for Radiological 3269100100012 Protection 3269100100013 REFERENCE (J,JRN,288,143,2011) 3269100100014 #doi:10.1007/s10967-010-0963-0 3269100100015 FACILITY (NGEN,3CPRLNZ) The ZF-300-II intense neutron 3269100100016 generator at Lanzhou University 3269100100017 SAMPLE About 3 g of HfO2 powder of natural isotopic 3269100100018 composition (>99.95% pure) was pressed at 10 ton/cm2, 3269100100019 and a pellet, 0.3 cm thick and 2.0 cm in diameter was 3269100100020 obtained. 3269100100021 DETECTOR (HPGE) CH8403 coaxial high-purity germanium detector 3269100100022 made in the People's Republic of China with a 3269100100023 relative efficiency of 20% and an energy resolution 3269100100024 of 3 keV at at 1332 keV gamma ray from Co-60. 3269100100025 (SIBAR) The Au-Si surface barrier detector used in 3269100100026 135 deg. accompanying alpha particle tube was at a 3269100100027 distance of 119.7 cm from the target. 3269100100028 METHOD (ACTIV) Irradiation of the samples was carried out at 3269100100029 the ZF-300-II Intense Neutron Generator at Lanzhou 3269100100030 University and lasted about 22 h with a yield around 3269100100031 0.8E11 to 2.4E11 n/s. 3269100100032 MONITOR (41-NB-93(N,2N)41-NB-92-M,,SIG) 3269100100033 DECAY-MON (41-NB-92-M,10.15D,DG,934.4,0.9907) 3269100100034 MONIT-REF (,M.Wagner+,B,PH-DAT,13-5,1990) 3269100100035 The cross sections of monitor reaction were defined by 3269100100036 interpolation of the evaluated values of the reference 3269100100037 from "Physik Daten - Physics Data, Evaluation of Cross 3269100100038 Sections for 14 Important Neutron-Dosimetry Reactions. 3269100100039 Fachinformationszentrum Karlsruhe, Gesellschaft fur 3269100100040 wissenschaftlich-technische Information mbH, Federal 3269100100041 Republic of Germany, No. 13-5 (1990)". 3269100100042 INC-SOURCE (D-T) The tritium-titanium (T-Ti) target used in the 3269100100043 generator was 0.9 mg/cm2 thick. The effective source 3269100100044 neutron energy at irradiation position was determined 3269100100045 by the Nb/Zr method, and the uncertainty in the 3269100100046 neutron energy at around 5 cm was estimated to 3269100100047 be 200 keV from a consideration of the sample sizes, 3269100100048 beam diameter of about 3-4mm, and the uncertainty in 3269100100049 the Nb/Zr method. 3269100100050 ERR-ANALYS (ERR-T) Total uncertainty of the measurement. 3269100100051 (ERR-S,0.1,15.) Counting statistics is between 0.1% 3269100100052 and 15%. 3269100100053 (MONIT-ERR) Standard cross sections uncertainty (1.%) 3269100100054 (ERR-1,2.,3.) Detector efficiency (2%-3%) 3269100100055 (ERR-2) Weight of sample (0.1%) 3269100100056 (ERR-3) Self-absorption of gamma-ray (0.5%) 3269100100057 (ERR-4,0.,5.) Coincidence sum effect of cascade 3269100100058 gamma-rays (0%-5%) 3269100100059 (ERR-5,0.1,1.0) Uncertainties of irradiation, cooling 3269100100060 and measuring times (0.1%-1.0%) 3269100100061 CORRECTION Measurements were corrected for gamma-ray 3269100100062 attenuations, random coincidence (pile-up), dead time 3269100100063 and fluctuation of neutron flux. The neutron fluence 3269100100064 rate was monitored by the accompanying alpha-particle 3269100100065 so that corrections were made for small variations in 3269100100066 the yield. 3269100100067 STATUS (TABLE) All measured reactions data are taken from 3269100100068 Table2 at page 147 in J,JRN,288,143-148,2011. And the 3269100100069 monitor reaction data are taken from the page 147 in 3269100100070 J,JRN,288,143-148,2011. 3269100100071 HISTORY (20120209C) Compiled by Guochang CHEN (CNDC); 3269100100072 ENDBIB 70 0 3269100100073 COMMON 3 3 3269100100074 ERR-2 ERR-3 EN-ERR 3269100100075 PER-CENT PER-CENT MEV 3269100100076 0.1 0.5 0.2 3269100100077 ENDCOMMON 3 0 3269100100078 ENDSUBENT 77 0 3269100199999 SUBENT 32691002 20120209 31543269100200001 BIB 2 4 3269100200002 REACTION 1(72-HF-0(N,X)72-HF-178-M2,,SIG) 3269100200003 2(72-HF-0(N,X)72-HF-179-M2,,SIG) 3269100200004 DECAY-DATA1(72-HF-178-M2,31.YR,DG,574.219,0.899) 3269100200005 2(72-HF-179-M2,25.05D,DG,362.55,0.411) 3269100200006 ENDBIB 4 0 3269100200007 NOCOMMON 0 0 3269100200008 DATA 7 1 3269100200009 EN DATA 1ERR-T DATA 2ERR-T MONIT 3269100200010 MONIT-ERR 3269100200011 MEV MB MB MB MB MB 3269100200012 MB 3269100200013 14.8 7.2 3.0 18.6 3.4 459.73269100200014 5.0 3269100200015 ENDDATA 6 0 3269100200016 ENDSUBENT 15 0 3269100299999 ENDENTRY 2 0 3269199999999