ENTRY 23177 20160916 22522317700000001 SUBENT 23177001 20160916 22522317700100001 BIB 18 79 2317700100002 AUTHOR (I.A.Reyhancan) 2317700100003 TITLE Measurements and model calculations of activation cross2317700100004 sections for Th-232(n,2n)Th-231 reaction between 13.57 2317700100005 and 14.83 MeV neutrons. 2317700100006 REFERENCE (J,ANE,38,2359,2011) Main reference. 2317700100007 #doi:10.1016/j.anucene.2011.07.032 2317700100008 INSTITUTE (2TUKSTU) 2317700100009 PART-DET (G) Decay gamma-rays. 2317700100010 REL-REF (M,21807001,A.Pavlik+,J,JP/G,8,1283,1982) 2317700100011 90Zr(n,2n)89Zr c-s data used in ZR/Nb method. 2317700100012 (M,10709001,D.R.Nethaway,J,JIN,40,1285,1978) 2317700100013 93Nb(n,2n)92mNb c-s data used in ZR/Nb method. 2317700100014 (M,,V.E.Lewis+,J,NIM,174,141,1980) 2317700100015 Zr/Nb ratio method . 2317700100016 (M,22474001,M.Subasi+,J,NSE,122,(1),423,1996) 2317700100017 Details of Zr/Nb method. 2317700100018 Decay data from two references: 2317700100019 (R,,R.B.Firestone+,B,FIRESTONE,,1996) and 2317700100020 J.K.Tuli,2005. Nuclear Wallet Cards, 7th ed.,BNL,USA. 2317700100021 FACILITY (VDG,2TUKCNA) SAMES T-400 neutron generator. 2317700100022 Beam current is kept at about 200 microA with 2317700100023 accelerator voltage of 250 kV. 2317700100024 INC-SOURCE (D-T) Solid tritium target. 2317700100025 INC-SPECT The effective energy of incident neutron at each 2317700100026 irradiation position has been previously determined by 2317700100027 the ratio of 90Zr(n,2n)89Zr (3.27 d) (Pavlik+,1982) 2317700100028 and 93Nb(n,2n)92mNb (10.15 d) (Nethaway,1978) reaction 2317700100029 cross sections (the Zr/Nb ratio method) (Lewis and 2317700100030 Zieba, 1980) and are given in detail in Subasi+,1996. 2317700100031 Effective average neutron flux at the sample position 2317700100032 was determined by measuring the activity induced via 2317700100033 27Al(n,alpha)24-Na monitor reaction. 2317700100034 At the irradiation place (70 mm from neutron source) 2317700100035 the neutron fluxes are ranged from 1E+7 to 6.E+7 2317700100036 n/cm**2/s, depending on neutron target condition. 2317700100037 MONITOR (13-AL-27(N,A)11-NA-24,,SIG) 2317700100038 MONIT-REF (,,3,JENDL-4.0,,2010) Cross sections in the same 2317700100039 neutron energies were obtained by polynomial fit to 2317700100040 JENDL-4.0 data file. 2317700100041 DECAY-MON (11-NA-24,14.951HR,DG,1368.63,1.00) 2317700100042 SAMPLE Thorium foils of 99.885% purity, 12.7 mm diameter, 2317700100043 0.0508 mm thickness, about 0.085 g weight were placed 2317700100044 on a thin aluminum frame fixed on the target holder 2317700100045 inclined at the angle of 45deg. 2317700100046 Thorium foil in each position was sandwiched between 2317700100047 two Al monitor foils of 1 mm thickness. 2317700100048 Isotopic abundances 100%. 2317700100049 METHOD (ACTIV) The angles of irradiation positions to the 2317700100050 deuteron beam were 0, 30, 60, 90, 120, 130 deg, which 2317700100051 covered the neutron energies 14.83, 14.75, 14.52, 2317700100052 14.15, 13.75, 13.57 MeV, respectively. 2317700100053 Irradiation time 1 hr. 2317700100054 DETECTOR (SCIN) During irradiation, the neutron flux was 2317700100055 monitored with plastic scintillation detector NE102A, 2317700100056 placed under the neutron-producing target. 2317700100057 (HPGE) Gamma activities induced in the Al and Th foils 2317700100058 were measured by high-resolution gamma-ray spectrometer2317700100059 with HpGe detector ORTEC GMX10180, 0.60 keV FWHM at 2317700100060 5.9 keV, 1.80 keV FWHM at 1333 keV. 2317700100061 Acrylic plate of 10 mm thickness was placed in front of2317700100062 the detector to block the beta particles from samples. 2317700100063 CORRECTION Self-absorption of gamma ray in the foils, attenuation 2317700100064 of the gamma rays in beta absorber, random coincidences2317700100065 of the gamma peaks, dead time, fluctuations of neutron 2317700100066 flux during irradiation and contributions from low 2317700100067 energy neutrons (about 17%). 2317700100068 Measured activities are corrected for self absorption 2317700100069 of gamma rays as 4%, 83% (757.2 cm**(-1), linear 2317700100070 attenuation coefficient of photon energy with 25.64 keV2317700100071 for Th foils) irradiated Al and Th foils respectively. 2317700100072 ANALYSIS Full energy peak (FEP) areas were collected 2317700100073 until a required uncertainty (1% to 2%) for the 2317700100074 gamma-ray peaks of interest. 2317700100075 The gamma peaks areas were evaluated by using the 2317700100076 SAMPO90 program. 2317700100077 HISTORY (20120103C) M.M. 2317700100078 (20160916A) SD:Values of ERR-5 were added to Subent 0022317700100079 (Data were received from Iskender A. Reyhancan on 2317700100080 2016-07-22). Other small corrections. 2317700100081 ENDBIB 79 0 2317700100082 NOCOMMON 0 0 2317700100083 ENDSUBENT 82 0 2317700199999 SUBENT 23177002 20160916 22522317700200001 BIB 5 21 2317700200002 REACTION (90-TH-232(N,2N)90-TH-231,,SIG) 2317700200003 DECAY-DATA (90-TH-231,25.52HR,DG,25.64,0.145) 2317700200004 HL = 25.52 +-0.01; E-gamma = 25.64 +-0.02, 2317700200005 gamma ray intensity (14.5 +-0.3) %. 2317700200006 ERR-ANALYS Uncertainties were assumed to be uncorrelated. 2317700200007 (ERR-1) Error of foil weight. 2317700200008 (ERR-2) Error of concentration of the element. 2317700200009 (ERR-3) Error of counting solid angle and intrinsic 2317700200010 efficiency of the gamma detector. 2317700200011 (ERR-4) Error of self absorption of the gamma ray. 2317700200012 (ERR-5) Error of full-energy photo-peak area. 2317700200013 (ERR-6) Error of effective neutron flux (reference 2317700200014 cross section) 2317700200015 (ERR-7) Error of irradiation, cooling and measuring 2317700200016 times. 2317700200017 (ERR-8) Error of neutron flux fluctuation. 2317700200018 (ERR-9) Error of relative gamma-ray intensity. 2317700200019 (ERR-T) Total error 5.0 - 5.2 %. 2317700200020 STATUS (TABLE) Table 4 of J,ANE,38,2359,2011. 2317700200021 MONIT values from Table 1. ERR-5 values from author. 2317700200022 HISTORY (20160916A) SD: Values for ERR-5 were added. 2317700200023 ENDBIB 21 0 2317700200024 COMMON 11 6 2317700200025 ERR-1 ERR-2 ERR-3 ERR-4 ERR-6 ERR-7 2317700200026 ERR-8 ERR-9 ERR-HL ERR-IDD ERR-EDD 2317700200027 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2317700200028 PER-CENT PER-CENT HR NO-DIM KEV 2317700200029 0.1 0.1 3.0 0.2 3.0 0.1 2317700200030 1. 2. 0.01 0.003 0.02 2317700200031 ENDCOMMON 6 0 2317700200032 DATA 6 6 2317700200033 EN EN-ERR DATA ERR-T MONIT ERR-5 2317700200034 MEV MEV MB MB MB PER-CENT 2317700200035 13.57 0.04 1970.0 118. 125.59 2.6 2317700200036 13.75 0.05 1568.8 79. 124.47 1.5 2317700200037 14.15 0.07 1556.7 77. 121.31 1.2 2317700200038 14.52 0.09 1215.7 61. 116.76 1.5 2317700200039 14.75 0.09 1174.2 59. 112.73 1.5 2317700200040 14.83 0.10 1089.4 55. 111.06 1.6 2317700200041 ENDDATA 8 0 2317700200042 ENDSUBENT 41 0 2317700299999 ENDENTRY 2 0 2317799999999