ENTRY 32692 20110907 31543269200000001 SUBENT 32692001 20110907 31543269200100001 BIB 16 49 3269200100002 TITLE Cross-section measurements for the (n,a) reactions 3269200100003 on stannum isotopes at the neutron energies from 13.5 3269200100004 to 14.6 MeV 3269200100005 AUTHOR (Zhongsheng Pu,Guanqiang Song,Kangkang Fan,Peng Yang) 3269200100006 INSTITUTE (3CPRLNZ) 3269200100007 REFERENCE (J,JRN,288,(2),507,201105) 3269200100008 #doi:10.1007/s10967-010-0945-2 3269200100009 FACILITY (NGEN,3CHPLNZ) ZF-300-II Intense Neutron Generator at 3269200100010 Lanzhou University, the yield was about 3*e10~4*e10 3269200100011 n/s. 3269200100012 INC-SOURCE (D-T) The tritium-titanium (T-Ti) target used in the 3269200100013 generator was 1.35 mg/cm2 thick. An effective 3269200100014 deuteron beam energy was 135 KeV and a beam current 3269200100015 was 500 micro-A. 3269200100016 DETECTOR (HPGE)CH8403 coaxial high-purity germanium detector 3269200100017 made in the People Republic of China, sensitive 3269200100018 volume was 110 cm3, with a relative efficiency of 20% 3269200100019 and an energy resolution of 3 KeV at 1332 KeV. 3269200100020 SAMPLE The groups of samples were placed at 0, 45, 90, 135 3269200100021 degree angles relative to the beam direction. The 3269200100022 samples in each group were sandwiched between two Al 3269200100023 or two Nb foils. 3269200100024 METHOD (ACTIV) 3269200100025 MONITOR (41-NB-93(N,2N)41-NB-92-M,,SIG) 3269200100026 (13-AL-27(N,A)11-NA-24,,SIG) 3269200100027 DECAY-MON (41-NB-92-M,10.15D,DG,934.4,0.9907) 3269200100028 (11-NA-24,14.959HR,DG,1368.6,1.00) 3269200100029 MONIT-REF (,M.Wagner+,B,PH-DAT,13-5,1990) 3269200100030 The cross sections of monitor reaction were defined by 3269200100031 interpolation of the evaluated values of the reference 3269200100032 from "Physik Daten - Physics Data, Evaluation of Cross 3269200100033 Sections for 14 Important Neutron-Dosimetry Reactions. 3269200100034 Fachinformationszentrum Karlsruhe, Gesellschaft fur 3269200100035 wissenschaftlich-technische Information mbH, Federal 3269200100036 Republic of Germany, No. 13-5 (1990)". 3269200100037 ERR-ANALYS (ERR-T) Total uncertainty include the uncertainty of 3269200100038 counting statistics, detector efficiency, monitor 3269200100039 reaction cross sections, weight of samples, self- 3269200100040 absorption of gamma-ray, coincidence summing effect of 3269200100041 cascade gamma-rays, sample geometry and effect of the 3269200100042 scattering neutrons. 3269200100043 CORRECTION The neutron flux was monitored by a uranium fission 3269200100044 chamber so that corrections were made for small 3269200100045 variations in the yield. The sample gamma-ray 3269200100046 self-absorption, neutron flux fluctuation and sample 3269200100047 geometry were corrected. 3269200100048 HISTORY (20110907C)Compiled by Jimin WANG(CNDC). 3269200100049 STATUS (TABLE) All measured reactions data are taken from 3269200100050 Table2 at page 509 in J,JRN,288,(2),201105. 3269200100051 ENDBIB 49 0 3269200100052 NOCOMMON 0 0 3269200100053 ENDSUBENT 52 0 3269200199999 SUBENT 32692002 20110907 31543269200200001 BIB 3 3 3269200200002 REACTION (50-SN-118(N,A)48-CD-115,,SIG) 3269200200003 DECAY-DATA (48-CD-115,53.46HR,DG,527.9,0.274) 3269200200004 SAMPLE (50-SN-118,NAT=0.2423) 3269200200005 ENDBIB 3 0 3269200200006 NOCOMMON 0 0 3269200200007 DATA 4 3 3269200200008 EN EN-ERR DATA ERR-T 3269200200009 MEV MEV MB MB 3269200200010 13.5 0.3 0.63 0.05 3269200200011 14.4 0.3 0.98 0.06 3269200200012 14.6 0.3 1.65 0.08 3269200200013 ENDDATA 5 0 3269200200014 ENDSUBENT 13 0 3269200299999 SUBENT 32692003 20110907 31543269200300001 BIB 3 3 3269200300002 REACTION (50-SN-120(N,A)48-CD-117-G,,SIG) 3269200300003 DECAY-DATA (48-CD-117-G,2.49HR,DG,273.349,0.279) 3269200300004 SAMPLE (50-SN-120,NAT=0.3259) 3269200300005 ENDBIB 3 0 3269200300006 NOCOMMON 0 0 3269200300007 DATA 4 3 3269200300008 EN EN-ERR DATA ERR-T 3269200300009 MEV MEV MB MB 3269200300010 14.1 0.2 0.13 0.04 3269200300011 14.4 0.3 0.23 0.05 3269200300012 14.6 0.3 0.25 0.05 3269200300013 ENDDATA 5 0 3269200300014 ENDSUBENT 13 0 3269200399999 SUBENT 32692004 20110907 31543269200400001 BIB 3 3 3269200400002 REACTION (50-SN-120(N,A)48-CD-117-M,,SIG) 3269200400003 DECAY-DATA (48-CD-117-M,3.36HR,DG,564.397,0.147) 3269200400004 SAMPLE (50-SN-120,NAT=0.3259) 3269200400005 ENDBIB 3 0 3269200400006 NOCOMMON 0 0 3269200400007 DATA 4 3 3269200400008 EN EN-ERR DATA ERR-T 3269200400009 MEV MEV MB MB 3269200400010 13.5 0.3 0.16 0.05 3269200400011 14.1 0.2 0.18 0.05 3269200400012 14.4 0.3 0.21 0.06 3269200400013 ENDDATA 5 0 3269200400014 ENDSUBENT 13 0 3269200499999 ENDENTRY 4 0 3269299999999