ENTRY 32715 20140514 31643271500000001 SUBENT 32715001 20140514 31643271500100001 BIB 13 61 3271500100002 TITLE Measurements of activation cross-sections for the 3271500100003 101Ru(n,p)101Tc reaction for neutrons with energies 3271500100004 between 13 and 15 MeV 3271500100005 AUTHOR (Junhua Luo,Jiuning Han,Rong Liu,Li Jiang,Suhong Ge, 3271500100006 Zhenlai Liu,Guihua Sun) 3271500100007 INSTITUTE (3CPRHXU,3CPRBJG,3CPRNPC) 3271500100008 REFERENCE (J,JRN,296,1225,2013) 3271500100009 #doi:10.1007/s10967-012-2341-6 3271500100010 FACILITY (NGEN,3CPRNPC) K-400 neutron generator 3271500100011 SAMPLE About 7 gram of ruthenium powder of natural isotopic 3271500100012 composition (99.99 % pure) was pressed as a pellet at 3271500100013 10 ton/cm2, 0.2 cm thick and 2.0 cm in diameter. 3271500100014 Monitor foils of Nb (99.99% pure, 0.2 mm thick) and 3271500100015 Al (99.999% pure, 0.04 mm thick) of the same diameter 3271500100016 as the pellets were then attached in front and at the 3271500100017 back of each sample. 3271500100018 DETECTOR (HPGE) The crystal geometry is 70.1 x 72.3 mm in 3271500100019 diameter and length. The relative efficiency is about 3271500100020 68%, and energy resolution is 1.69 keV at 1332 keV 3271500100021 gamma ray from Co-60. The efficiency of the detector 3271500100022 was pre-calibrated using various standard gamma 3271500100023 sources such as Na-24, Nb-92m, Tc-101, Mo-101. 3271500100024 (FISCH) The neutron flux was monitored by a uranium 3271500100025 fission chamber. 3271500100026 METHOD (ACTIV) Irradiation of the samples was lasted 128 min 3271500100027 with a yield around 4E10 to 5E10 n/s, and cooled for 3271500100028 5-10 min. The groups of samples were placed at 0deg., 3271500100029 90deg. or 135deg. angles relative to the beam 3271500100030 direction and centered about the T-Ti target at 3271500100031 distances of around 4 cm. 3271500100032 INC-SOURCE (D-T) An effective deuteron beam energy of 134 keV 3271500100033 and beam current of 230 uA were used to produce 3271500100034 neutrons. And the tritium-titanium (T-Ti) target used 3271500100035 in the generator was 2.18 mg/cm2 thick. 3271500100036 ERR-ANALYS (ERR-T) Total uncertainty of cross section result 3271500100037 from counting statistics, standard cross sections 3271500100038 uncertainties, detector efficiency, weight of samples, 3271500100039 self-absorption of gamma-rays and the coincidence sum 3271500100040 effect of cascade gamma-rays, the uncertainties of 3271500100041 irradiation, cooling and measuring times. And some 3271500100042 other errors contribution form the parameters of the 3271500100043 measured nuclei and standard nuclei, such as, 3271500100044 uncertainties of the branching ratio of the 3271500100045 characteristic gamma rays, uncertainties of the half 3271500100046 life of the radioactive product nuclei and so on all 3271500100047 are considered. 3271500100048 (ERR-S,0.1,15.) Counting statistics (0.1-15%) 3271500100049 (ERR-1,2.,3.) Detector efficiency (2-3%) 3271500100050 (ERR-2) Weight of samples (0.1%) 3271500100051 (ERR-3) Self-absorption of gamma-ray (0.5%) 3271500100052 (ERR-4,0.,5.) The coincidence sum effect of cascade 3271500100053 gamma-rays (0-5%) 3271500100054 (ERR-5,0.1,1.0) The uncertainties of irradiation, 3271500100055 cooling and measuring times (0.1-1.0%) 3271500100056 CORRECTION Measurements were corrected for gamma-ray 3271500100057 attenuations, random coincidence (pile-up), dead time 3271500100058 and fluctuation of neutron flux. 3271500100059 STATUS (TABLE) All measured reactions data and monitor 3271500100060 reaction data are taken from Table 2 at page 1228 in 3271500100061 J,JRN,296,1225,2013. 3271500100062 HISTORY (20140514C) Compiled by CHEN Guochang (CNDC) 3271500100063 ENDBIB 61 0 3271500100064 COMMON 2 3 3271500100065 ERR-2 ERR-3 3271500100066 PER-CENT PER-CENT 3271500100067 0.1 0.5 3271500100068 ENDCOMMON 3 0 3271500100069 ENDSUBENT 68 0 3271500199999 SUBENT 32715002 20140514 31643271500200001 BIB 7 12 3271500200002 REACTION (44-RU-101(N,P)43-TC-101,,SIG,,,DERIV) 3271500200003 DECAY-DATA (43-TC-101,14.22MIN,DG,306.85,0.88) 3271500200004 SAMPLE (44-RU-101,NAT=0.170) 3271500200005 (44-RU-102,NAT=0.316) 3271500200006 ASSUMED (ASSUM,44-RU-102(N,X)43-TC-101,,SIG) 3271500200007 REL-REF (R,,Y.Kasugai+,S,JAERI-M-92-027,268,1992) 3271500200008 104Ru(n,a)101Mo and 102Ru(n,x) 101Tc cross sections 3271500200009 adopted in the data reduction given. 3271500200010 ANALYSIS The data for 101Ru(n,p)101Tc reaction cross sections 3271500200011 are corrected for the calculated contributions of the 3271500200012 104Ru(n,a)101Mo and the 102Ru(n,d)101Tc reactions. 3271500200013 STATUS (DEP,31715003) natRu(n,x)101Tc cross section given. 3271500200014 ENDBIB 12 0 3271500200015 NOCOMMON 0 0 3271500200016 DATA 6 3 3271500200017 EN EN-ERR DATA ERR-T ASSUM ASSUM-ERR 3271500200018 MEV MEV MB MB MB MB 3271500200019 13.5 0.2 15.7 2.0 0.63 0.073271500200020 14.1 0.2 18.4 2.7 1.23 0.103271500200021 14.8 0.2 22.0 2.4 2.77 0.193271500200022 ENDDATA 5 0 3271500200023 ENDSUBENT 22 0 3271500299999 SUBENT 32715003 20140514 31643271500300001 BIB 9 13 3271500300002 REACTION (44-RU-0(N,X)43-TC-101,,SIG) 3271500300003 DECAY-DATA (43-TC-101,14.22MIN,DG,306.85,0.880) 3271500300004 (42-MO-101,14.61MIN,DG,191.92,0.190) 3271500300005 SAMPLE (44-RU-104,NAT=0.187) 3271500300006 MONITOR ((MONIT1)41-NB-93(N,2N)41-NB-92-M,,SIG) 3271500300007 ((MONIT2)13-AL-27(N,A)11-NA-24,,SIG) 3271500300008 DECAY-MON ((MONIT1)41-NB-92-M,10.15D,DG,934.4,0.9907) 3271500300009 ((MONIT2)11-NA-24,14.959HR,DG,1368.6,1.00) 3271500300010 MONIT-REF (,M.Wagner+,B,PH-DAT,13-5,1990) 3271500300011 ASSUMED (ASSUM,44-RU-104(N,A)42-MO-101,,SIG) 3271500300012 ERR-ANALYS (MONIT1-ERR) Standard cross sections (1.%) 3271500300013 (MONIT2-ERR) Standard cross sections (1.%) 3271500300014 CORRECTION 104Ru(n,a)101Mo->101Tc contribution subtracted. 3271500300015 ENDBIB 13 0 3271500300016 NOCOMMON 0 0 3271500300017 DATA 10 3 3271500300018 EN EN-ERR DATA ERR-T ASSUM ASSUM-ERR 3271500300019 MONIT1 MONIT1-ERR MONIT2 MONIT2-ERR 3271500300020 MEV MEV MB MB MB MB 3271500300021 MB MB MB MB 3271500300022 13.5 0.2 2.87 0.31 1.47 0.263271500300023 457.9 6.8 125.7 0.8 3271500300024 14.1 0.2 3.52 0.42 1.92 0.303271500300025 459.8 6.8 121.6 0.6 3271500300026 14.8 0.2 4.62 0.34 2.55 0.333271500300027 459.7 5.0 111.9 0.5 3271500300028 ENDDATA 10 0 3271500300029 ENDSUBENT 28 0 3271500399999 ENDENTRY 3 0 3271599999999