ENTRY 32710 20130416 31603271000000001 SUBENT 32710001 20130416 31603271000100001 BIB 16 57 3271000100002 TITLE Cross-sections for (n,2n) and (n,p) reactions on 3271000100003 neodymium isotopes and 160Gd(n,a)157Sm at neutron 3271000100004 energy between 13.5 and 14.7 MeV 3271000100005 AUTHOR (Yanbin Zhang,Liangyong Zhao,Xiangzhong Kong,Rong Liu, 3271000100006 Li Jiang) 3271000100007 INSTITUTE (3CPRLNZ,3CPRNPC) 3271000100008 REFERENCE (J,ANE,53,99,2013) 3271000100009 #doi:10.1016/j.anucene.2012.10.008 3271000100010 FACILITY (NGEN,3CPRNPC) TD-300 Neutron Generator for sample 3271000100011 irradiations. 3271000100012 SAMPLE Spectroscopically pure neodymium oxide and gadolinium 3271000100013 oxide were made into circular samples with a diameter 3271000100014 of 2.0 cm and thickness of 0.5 cm, which were 3271000100015 sandwiched by two Al foil with the same diameter. 3271000100016 Al metal purity was better than 99.99%. They were 3271000100017 placed at 0, 90 and 135 degree angles relative to the 3271000100018 deuteron beam direction and centered about the T-Ti 3271000100019 target at distances of 1.2-3.0 cm. 3271000100020 DETECTOR (HPGE) A well-calibrated GEM-60P coaxial high-purity 3271000100021 germanium (HPGe) detector was used with 70.1x72.3 mm 3271000100022 in diameter and length for the crystal. The relative 3271000100023 efficiency was about 68%, and the energy resolution 3271000100024 was about 1.69 keV (FWHM) at 1.33 MeV. 3271000100025 METHOD (ACTIV) Irradiation of the samples was carried out and 3271000100026 lasted 40 min with a neutron yield of about 3E10 to 3271000100027 5E10 n/s. The neutron flux was monitored by the 3271000100028 accompanying alpha particles. 3271000100029 MONITOR (13-AL-27(N,A)11-NA-24,,SIG) 3271000100030 DECAY-MON (11-NA-24,14.959HR,DG,1368.633,1.0) 3271000100031 MONIT-REF (,M.Wagner+,B,PH-DAT,13-5,1990) 3271000100032 The cross section values of the monitor reaction were 3271000100033 obtained by interpolating the evaluated work of the 3271000100034 literature. 3271000100035 INC-SOURCE (D-T) The solid tritium-titanium (T-Ti) target was 3271000100036 used with 2.4 mg/cm2 in thickness and with a effective 3271000100037 deuteron beam of 121 keV and beam current of 300 uA. 3271000100038 Neutron energies in the measurements were determined 3271000100039 by cross section ratios for 93Nb(n,2n)92mNb and 3271000100040 90Zr(n,2n)89m+gZr reactions. 3271000100041 ERR-ANALYS (ERR-T) Total uncertainty of measurement. 3271000100042 (ERR-S,1.,5.) Statistical uncertainties. 3271000100043 (ERR-1) Uncertainty of detector efficiency. 3271000100044 (ERR-2,,3.) Uncertainty of the coincidence sum effect 3271000100045 of cascade gamma-ray. 3271000100046 (ERR-3,,0.5) Uncertainty of sample weights and self- 3271000100047 absorption of gamma-ray. 3271000100048 (ERR-4,,0.5) Uncertainties from irradiation, cooling 3271000100049 and measurement time. 3271000100050 (MONIT-ERR) Uncertainty of monitor cross section. 3271000100051 CORRECTION Dead-time and pulse pileup corrections were less than 3271000100052 2% in all cases. While determining the activities of 3271000100053 the gamma-rays, corrections for self-absorption of the 3271000100054 gamma-rays, real coincidence summing and geometry were 3271000100055 made. 3271000100056 HISTORY (20130416C) Compiled by WANG Jimin (CNDC). 3271000100057 STATUS (TABLE) All measured data were taken from Table 2 at 3271000100058 page 101 in J,ANE,53,(1),99,2013. 3271000100059 ENDBIB 57 0 3271000100060 COMMON 3 3 3271000100061 EN-RSL ERR-1 MONIT-ERR 3271000100062 MEV PER-CENT PER-CENT 3271000100063 0.2 2.0 1. 3271000100064 ENDCOMMON 3 0 3271000100065 ENDSUBENT 64 0 3271000199999 SUBENT 32710002 20130416 31603271000200001 BIB 3 3 3271000200002 REACTION (60-ND-146(N,P)59-PR-146,,SIG) 3271000200003 SAMPLE (60-ND-146,NAT=0.172) 3271000200004 DECAY-DATA (59-PR-146,24.15MIN,DG,453.888,0.48) 3271000200005 ENDBIB 3 0 3271000200006 NOCOMMON 0 0 3271000200007 DATA 3 3 3271000200008 EN DATA ERR-T 3271000200009 MEV MB MB 3271000200010 13.5 3.06 0.36 3271000200011 14.1 3.92 0.37 3271000200012 14.7 4.93 0.47 3271000200013 ENDDATA 5 0 3271000200014 ENDSUBENT 13 0 3271000299999 SUBENT 32710003 20130416 31603271000300001 BIB 3 3 3271000300002 REACTION (60-ND-142(N,P)59-PR-142,,SIG) 3271000300003 SAMPLE (60-ND-142,NAT=0.272) 3271000300004 DECAY-DATA (59-PR-142-G,19.12HR,DG,1575.6,0.037) 3271000300005 ENDBIB 3 0 3271000300006 NOCOMMON 0 0 3271000300007 DATA 3 1 3271000300008 EN DATA ERR-T 3271000300009 MEV MB MB 3271000300010 14.7 13.81 1.50 3271000300011 ENDDATA 3 0 3271000300012 ENDSUBENT 11 0 3271000399999 SUBENT 32710004 20130416 31603271000400001 BIB 4 4 3271000400002 REACTION (60-ND-142(N,2N)60-ND-141-M,,SIG) 3271000400003 SAMPLE (60-ND-142,NAT=0.272) 3271000400004 DECAY-DATA (60-ND-141-M,62.0SEC,DG,756.51,0.91395) 3271000400005 COMMENT Samples were measured immediately after irradiation. 3271000400006 ENDBIB 4 0 3271000400007 NOCOMMON 0 0 3271000400008 DATA 3 1 3271000400009 EN DATA ERR-T 3271000400010 MEV MB MB 3271000400011 13.5 580. 59. 3271000400012 ENDDATA 3 0 3271000400013 ENDSUBENT 12 0 3271000499999 SUBENT 32710005 20130416 31603271000500001 BIB 4 5 3271000500002 REACTION (60-ND-142(N,2N)60-ND-141-G,,SIG) 3271000500003 SAMPLE (60-ND-142,NAT=0.272) 3271000500004 DECAY-DATA (60-ND-141-G,2.49HR,DG,145.45,0.0024) 3271000500005 CORRECTION Corrected for the contribution from the 3271000500006 142-Nd(n,2n)141m-Nd reaction. 3271000500007 ENDBIB 5 0 3271000500008 NOCOMMON 0 0 3271000500009 DATA 3 1 3271000500010 EN DATA ERR-T 3271000500011 MEV MB MB 3271000500012 13.5 866. 88. 3271000500013 ENDDATA 3 0 3271000500014 ENDSUBENT 13 0 3271000599999 SUBENT 32710006 20130416 31603271000600001 BIB 3 4 3271000600002 REACTION (64-GD-160(N,A)62-SM-157,,SIG) 3271000600003 SAMPLE (64-GD-160,NAT=0.2186) 3271000600004 DECAY-DATA (62-SM-157,8.03MIN,DG,196.461,0.17) 3271000600005 (62-SM-157,8.03MIN,DG,197.870,0.56) 3271000600006 ENDBIB 4 0 3271000600007 NOCOMMON 0 0 3271000600008 DATA 3 2 3271000600009 EN DATA ERR-T 3271000600010 MEV MB MB 3271000600011 14.1 0.52 0.09 3271000600012 14.7 0.59 0.09 3271000600013 ENDDATA 4 0 3271000600014 ENDSUBENT 13 0 3271000699999 ENDENTRY 6 0 3271099999999