ENTRY 32690 20110906 31543269000000001 SUBENT 32690001 20110906 31543269000100001 BIB 16 70 3269000100002 TITLE Measurements of activation cross sections for 3269000100003 175Lu(n,a)172Tm, 176Lu(n,a)173Tm and 3269000100004 175Lu(n,p)175m+gYb reactions induced by neutrons 3269000100005 around 14 MeV 3269000100006 AUTHOR (Junhua Luo,Fei Tuo,Xiangzhong Kong) 3269000100007 INSTITUTE (3CPRHXU) School of Physics and Electromechanical 3269000100008 Engineering, Hexi University (Zhangye city, Gansu 3269000100009 Province) 3269000100010 (3CPRLNZ) School of Nuclear Science and Technology, 3269000100011 Lanzhou University 3269000100012 (3CPRCPR) National Institute for Radiological 3269000100013 Protection 3269000100014 REFERENCE (J,ANE,38,1693,2011) 3269000100015 #doi:10.1016/j.anucene.2011.04.014 3269000100016 FACILITY (NGEN,3CPRNPC) K-400 neutron generator at Chinese 3269000100017 Academy of Engineering Physics (CAEP) 3269000100018 SAMPLE About 3 g of Lu2O3 powder of natural isotopic 3269000100019 composition (>99.99% pure) was pressed at 10 ton/cm2, 3269000100020 and a pellet, 0.2 cm thick and 2.0 cm in diameter was 3269000100021 obtained. 3269000100022 DETECTOR (HPGE) The crystal geometry is 70.1 x 72.3 mm in 3269000100023 diameter and length. The relative efficiency is about 3269000100024 68%, and energy resolution is 1.69 keV at 1332 keV 3269000100025 gamma ray from Co-60. 3269000100026 METHOD (ACTIV) Irradiation of the samples was carried out at 3269000100027 the K-400 Neutron Generator and lasted 128 min with a 3269000100028 yield around 4E10 to 5E10 n/s. 3269000100029 MONITOR ((MONIT1)41-NB-93(N,2N)41-NB-92-M,,SIG) 3269000100030 ((MONIT2)13-AL-27(N,A)11-NA-24,,SIG) 3269000100031 DECAY-MON ((MONIT1)41-NB-92-M,10.15D,DG,934.4,0.9907) 3269000100032 ((MONIT2)11-NA-24,14.959HR,DG,1368.6,1.00) 3269000100033 MONIT-REF (,M.Wagner+,B,PH-DAT,13-5,1990) 3269000100034 The cross sections of monitor reaction were determined 3269000100035 by interpolation of the evaluated values of the 3269000100036 reference as "Physik Daten - Physics Data, Evaluation 3269000100037 of Cross Sections for 14 Important Neutron-Dosimetry 3269000100038 Reactions. Fachinformationszentrum Karlsruhe, 3269000100039 Gesellschaft fur wissenschaftlich-technische 3269000100040 Information mbH, Federal Republic of Germany, 3269000100041 No. 13-5 (1990)". 3269000100042 INC-SOURCE (D-T) The tritium-titanium (T-Ti) target used in the 3269000100043 generator was 2.18 mg/cm2 thick. The effective source 3269000100044 neutron energy at irradiation position was determined 3269000100045 by the Nb/Zr method, and the uncertainty in the 3269000100046 neutron energy at around 3 to 5 cm was estimated to 3269000100047 be 200 keV from a consideration of the sample sizes, 3269000100048 beam diameter of about 3-4 mm, and the uncertainty in 3269000100049 the Nb/Zr method. 3269000100050 ERR-ANALYS (ERR-S,1.,21.) Counting statistics is between 1.% and 3269000100051 21%. 3269000100052 (MONIT1-ERR) Standard cross sections uncertainty 3269000100053 (MONIT2-ERR) Standard cross sections uncertainty (1.%) 3269000100054 (ERR-1,2.,3.) Detector efficiency (2%-3%) 3269000100055 (ERR-2) Weight of sample (0.1%) 3269000100056 (ERR-3) Self-absorption of gamma-ray (0.5%) 3269000100057 (ERR-4,0.,5.) Coincidence sum effect of cascade 3269000100058 gamma-rays (0%-5%) 3269000100059 (ERR-5,0.1,1.0) Uncertainties of irradiation, cooling 3269000100060 and measuring times (0.1%-1.0%) 3269000100061 CORRECTION The neutron flux was monitored by a uranium fission 3269000100062 chamber so that corrections were made for small 3269000100063 variations in the yield. The self-absorption of the 3269000100064 sample at a given gamma-energy, the coincidence sum 3269000100065 effect of cascade gamma-rays in the investigated 3269000100066 nuclide and in the counting geometry were taken into 3269000100067 account in data analysis, respectively. 3269000100068 STATUS (TABLE) All measured reactions data and monitor 3269000100069 reaction data are taken from Table2 at page 1695 in 3269000100070 J,ANE,38,2011. 3269000100071 HISTORY (20110906C)Compiled by Guochang CHEN (CNDC); 3269000100072 ENDBIB 70 0 3269000100073 COMMON 3 3 3269000100074 ERR-2 ERR-3 EN-ERR 3269000100075 PER-CENT PER-CENT MEV 3269000100076 0.1 0.5 0.2 3269000100077 ENDCOMMON 3 0 3269000100078 ENDSUBENT 77 0 3269000199999 SUBENT 32690002 20110906 31543269000200001 BIB 3 3 3269000200002 REACTION (71-LU-175(N,A)69-TM-172,,SIG) 3269000200003 DECAY-DATA (69-TM-172,63.6HR,DG,1093.7,0.060) 3269000200004 SAMPLE (71-LU-175,NAT=0.9741) 3269000200005 ENDBIB 3 0 3269000200006 NOCOMMON 0 0 3269000200007 DATA 7 3 3269000200008 EN DATA DATA-ERR MONIT1 MONIT1-ERR MONIT2 3269000200009 MONIT2-ERR 3269000200010 MEV MB MB MB MB MB 3269000200011 MB 3269000200012 13.5 0.612 0.129 457.9 6.8 125.7 3269000200013 0.8 3269000200014 14.1 0.910 0.173 459.8 6.8 121.6 3269000200015 0.6 3269000200016 14.8 1.126 0.146 459.7 5.0 111.9 3269000200017 0.5 3269000200018 ENDDATA 10 0 3269000200019 ENDSUBENT 18 0 3269000299999 SUBENT 32690003 20110906 31543269000300001 BIB 3 3 3269000300002 REACTION (71-LU-176(N,A)69-TM-173,,SIG) 3269000300003 DECAY-DATA (69-TM-173,8.24HR,DG,398.9,0.879) 3269000300004 SAMPLE (71-LU-176,NAT=0.0259) 3269000300005 ENDBIB 3 0 3269000300006 NOCOMMON 0 0 3269000300007 DATA 7 3 3269000300008 EN DATA DATA-ERR MONIT1 MONIT1-ERR MONIT2 3269000300009 MONIT2-ERR 3269000300010 MEV MB MB MB MB MB 3269000300011 MB 3269000300012 13.5 0.704 0.049 457.9 6.8 125.7 3269000300013 0.8 3269000300014 14.1 0.876 0.070 459.8 6.8 121.6 3269000300015 0.6 3269000300016 14.8 0.919 0.046 459.7 5.0 111.9 3269000300017 0.5 3269000300018 ENDDATA 10 0 3269000300019 ENDSUBENT 18 0 3269000399999 SUBENT 32690004 20110906 31543269000400001 BIB 3 3 3269000400002 REACTION (71-LU-175(N,P)70-YB-175,,SIG) 3269000400003 DECAY-DATA (70-YB-175,4.185D,DG,396.3,0.064) 3269000400004 SAMPLE (71-LU-175,NAT=0.9741) 3269000400005 ENDBIB 3 0 3269000400006 NOCOMMON 0 0 3269000400007 DATA 7 3 3269000400008 EN DATA DATA-ERR MONIT1 MONIT1-ERR MONIT2 3269000400009 MONIT2-ERR 3269000400010 MEV MB MB MB MB MB 3269000400011 MB 3269000400012 13.5 6.4 0.4 457.9 6.8 125.7 3269000400013 0.8 3269000400014 14.1 7.4 0.6 459.8 6.8 121.6 3269000400015 0.6 3269000400016 14.8 8.2 0.5 459.7 5.0 111.9 3269000400017 0.5 3269000400018 ENDDATA 10 0 3269000400019 ENDSUBENT 18 0 3269000499999 ENDENTRY 4 0 3269099999999