ENTRY 32670 20090909 31423267000000001 SUBENT 32670001 20090909 31423267000100001 BIB 17 40 3267000100002 TITLE Activation cross-sections for 158Dy(n,p)158Tb, 3267000100003 156Dy(n,a)153Gd and 160Dy(n,p)160Tb reactions 3267000100004 induced by neutrons at 14.7MeV 3267000100005 AUTHOR (Junhua Luo, Xinxing Wang, Zhenlai Liu, Fei Tuo, 3267000100006 Xiangzhong Kong) 3267000100007 INSTITUTE (3CPRCPR) Hexi University 3267000100008 (3CPRLNZ) 3267000100009 REFERENCE (J,ARI,67,1892,2009) 3267000100010 FACILITY (FNS,3CPRLNZ) ZF-300-II Intense Neutron Generator 3267000100011 SAMPLE About 3g of Dy2O3 powder of natural isotopic 3267000100012 composition (>99.99% pure)was pressed at 10ton/cm2, 3267000100013 and a pellet,0.2cm thick and 2.0cm in diameter,was 3267000100014 obtained.Three such pellets were prepared. 3267000100015 DETECTOR (HPGE)CH8403 coaxial high-purity germanium detector 3267000100016 METHOD (ACTIV) 3267000100017 MONITOR ((MONIT)13-AL-27(N,A)11-NA-24,,SIG) 3267000100018 INC-SOURCE (D-T) 3267000100019 ERR-ANALYS (ERR-T) Total uncertainties 3267000100020 (ERR-S,1.,15.) Counting statistics (1-15%) 3267000100021 (ERR-1) Weight of samples (0.1%) 3267000100022 (ERR-2) Self-absorption of gamma-ray (0.5%) 3267000100023 (ERR-3,2.,3.) Detector efficiency (2-3%) 3267000100024 (ERR-4,0.,5.) Coincidence sum effect of cascade 3267000100025 gamma-rays (0-5%) 3267000100026 (ERR-5,0.1,1.) Irradiation, cooling and measuring 3267000100027 times (0.1-1%) 3267000100028 (EN-ERR) The uncertainty in the neutron energy at 3267000100029 5cm was estimated to be 200keV from a consideration 3267000100030 of the sample sizes,d+ beam diameter of about 3-4mm, 3267000100031 and the uncertainty in the Nb/Zr method 3267000100032 MONIT-REF ((MONIT),M.Wagner+,B,PH-DAT,13,(5),1990) 3267000100033 DECAY-MON ((MONIT)11-NA-24,14.959HR,DG,1368.6,1.0) 3267000100034 COMMENT By author: 3267000100035 Standard cross-sections uncertainties is 0.45%. 3267000100036 The value printed in p1894 (1%) is a misprint. 3267000100037 CORRECTION Measurements were corrected for gamma-ray attenuations,3267000100038 random coincidence(pile-up), deadtime and fluctuation 3267000100039 of neutron flux. 3267000100040 STATUS (APRVD) Approved by Luo Junhua in Sept.23,2009 3267000100041 HISTORY (20090909C) Compiled by Yu Hongwei 3267000100042 ENDBIB 40 0 3267000100043 COMMON 6 3 3267000100044 EN EN-ERR MONIT MONIT-ERR ERR-1 ERR-2 3267000100045 MEV MEV MB MB PER-CENT PER-CENT 3267000100046 14.7 0.2 111.9 0.5 0.1 0.5 3267000100047 ENDCOMMON 3 0 3267000100048 ENDSUBENT 47 0 3267000199999 SUBENT 32670002 20090909 31423267000200001 BIB 4 5 3267000200002 SAMPLE (66-DY-158,NAT=0.0010) 3267000200003 Cross section normalized by the abundance (0.10%) 3267000200004 REACTION (66-DY-158(N,P)65-TB-158,,SIG) 3267000200005 DECAY-DATA (65-TB-158-G,180.0YR,DG,944.09,0.440) 3267000200006 STATUS (TABLE) Data from the table.2 of this paper 3267000200007 ENDBIB 5 0 3267000200008 NOCOMMON 0 0 3267000200009 DATA 2 1 3267000200010 DATA ERR-T 3267000200011 MB MB 3267000200012 7.6 0.4 3267000200013 ENDDATA 3 0 3267000200014 ENDSUBENT 13 0 3267000299999 SUBENT 32670003 20090909 31423267000300001 BIB 4 5 3267000300002 SAMPLE (66-DY-156,NAT=0.0006) 3267000300003 Cross section normalized by the abundance (0.06%) 3267000300004 REACTION (66-DY-156(N,A)64-GD-153,,SIG) 3267000300005 DECAY-DATA (64-GD-153,241.6D,DG,103.18,0.214) 3267000300006 STATUS (TABLE) Data from the table.2 of this paper 3267000300007 ENDBIB 5 0 3267000300008 NOCOMMON 0 0 3267000300009 DATA 2 1 3267000300010 DATA ERR-T 3267000300011 MB MB 3267000300012 2.0 0.1 3267000300013 ENDDATA 3 0 3267000300014 ENDSUBENT 13 0 3267000399999 SUBENT 32670004 20090909 31423267000400001 BIB 4 5 3267000400002 SAMPLE (66-DY-160,NAT=0.0234) 3267000400003 Cross section normalized by the abundance (2.34%) 3267000400004 REACTION (66-DY-160(N,P)65-TB-160,,SIG) 3267000400005 DECAY-DATA (65-TB-160,72.3D,DG,298.58,0.255,DG,197.04,0.0502) 3267000400006 STATUS (TABLE) Data from the table.2 of this paper 3267000400007 ENDBIB 5 0 3267000400008 NOCOMMON 0 0 3267000400009 DATA 2 1 3267000400010 DATA ERR-T 3267000400011 MB MB 3267000400012 2.7 0.3 3267000400013 ENDDATA 3 0 3267000400014 ENDSUBENT 13 0 3267000499999 ENDENTRY 4 0 3267099999999