ENTRY 23201 20131010 22372320100000001 SUBENT 23201001 20131010 22372320100100001 BIB 19 84 2320100100002 TITLE Measurements of isomeric cross-sections for (n,alpha) 2320100100003 reaction on 144-Sm isotope for neutrons around 14 MeV. 2320100100004 AUTHOR (I.A.Reyhancan, A.Durusoy) 2320100100005 INSTITUTE (2TUKSTU) I.A.Reyhancan 2320100100006 (2TUKYTU) A.Durusoy 2320100100007 REFERENCE (J,NSE,174,202,2013) Data table. 2320100100008 REL-REF (R,21807001,A.Pavlik+,J,JP/G,8,1283,1982) 2320100100009 90Zr(n,2n)89Zr c-s data used in ZR/Nb method. 2320100100010 (R,10709001,D.R.Nethaway,J,JIN,40,1285,1978) 2320100100011 93Nb(n,2n)92mNb c-s data used in ZR/Nb method 2320100100012 (M,,V.E.Lewis+,J,NIM,174,141,1980) 2320100100013 Zr/Nb ratio method . 2320100100014 (M,22474001,M.Subasi+,J,NSE,122,(1),423,1996) 2320100100015 Details of Zr/Nb method. 2320100100016 FACILITY (LINAC,2TUKCNA) SAMES T-400 Neutron Generator in 2320100100017 combination with a Fast Sample Transfer System (FSTS), 2320100100018 which can deliver the sample from the irradiation 2320100100019 position to HpGe detector or vice versa within 0.5 s. 2320100100020 SAMPLE Sample pellets of 13 mm diameter, 8.5 mm thickness, 2320100100021 about 2 g weight were pressed from the natural, 2320100100022 high-purity (99.9%) Sm(2)O(3), and Al2O3 powders. 2320100100023 Water contents in the samples were removed by heating 2320100100024 the oxide materials up to 105 deg C, then they were 2320100100025 kept in a desiccator for 0.5 h to cool down to the room2320100100026 temperature; next they were filled into dry stainless 2320100100027 steel capsules and pressed to form a dense pellet; the 2320100100028 pellets were tightly packed into thin polyethylene 2320100100029 boxes and sealed-off. 2320100100030 INC-SOURCE (D-T) H-3(D,N)He-4 reaction . deuteron beam current 2320100100031 300 microA, accelerating voltage 250 kV. 2320100100032 INC-SPECT At the irradiation place (70 mm from neutron source), 2320100100033 neutron fluxes are measured to be from 0.9E+7 to 1.6E+72320100100034 n/cm2/s, depending on the neutron target condition. 2320100100035 METHOD (ACTIV) Six different positions around the target 2320100100036 holder inclined at 45 deg were used. The angles of 2320100100037 the irradiation positions along the deuteron beam were 2320100100038 0, 30, 60, 120, 130 deg,which correspond to the neutron2320100100039 energies 14.83, 14.75, 14.52, 14.15, 13.75, 13.57 MeV, 2320100100040 respectively. The effective energies of the incident 2320100100041 neutrons at each sample position were determined by the2320100100042 ratios of 90Zr(n,2n)89Zr (3.27 d) (Pavlik+, 1982) and 2320100100043 93Nb(n,2n)92mNb (10.15 d) (Nethaway, 1978) reaction 2320100100044 cross sections (the Zr/Nb ratio method) (Lewis+, 1980) 2320100100045 and procedure of the energy measurement is given in 2320100100046 detail in Subasi+(1996). 2320100100047 Acrylic plate of 10 mm thickness was placed in front of2320100100048 the detector to protect samples from beta particles. 2320100100049 and to minimize the photon absorption and production 2320100100050 bremsstrahlung. 2320100100051 DETECTOR (HPGE) Gamma counting system with HpGe detector 2320100100052 (Canberra, 82 cm3, 1.79 keV FWHM at 1333 keV), see 2320100100053 REL-REF of Subasi+,1996. 2320100100054 (SCIN) NE102A scintillation detector for neutron flux 2320100100055 determination . Calibrated by Al(2)O(3) sample. 2320100100056 High-resolution gamma-ray spectrometer was used to 2320100100057 measure gamma activity induced in the Al pellet. 2320100100058 MONITOR (13-AL-27(N,P)12-MG-27,,SIG) 2320100100059 DECAY-MON (12-MG-27,9.458MIN,DG,843.8,0.73) 2320100100060 or neutron flux monitoring. 2320100100061 MONIT-REF (,,3,ENDF/B-VII.0,,2006) 2320100100062 ANALYSIS Cyclic activation formula was used. 2320100100063 CORRECTION Self-absorption corrections . 2320100100064 Low-energy-neutron contribution- up to 10 %. 2320100100065 Attenuation of the gamma rays in a beta absorber. 2320100100066 Dead time. 2320100100067 ERR-ANALYS (ERR-T) Total error 21.5-47.2%) includes errors due to:2320100100068 (ERR-1) Sample weight, 2320100100069 (ERR-2) Concentration of the element, 2320100100070 (ERR-3) Isotopic abundance, 2320100100071 (ERR-4) Counting solid angle and intrinsic efficiency 2320100100072 of the gamma detector, 2320100100073 (ERR-S,21.,47.) Statistical uncertainty (full energy 2320100100074 photo-peak area), 2320100100075 (ERR-5) Neutron flux fluctuation, 2320100100076 (ERR-6) Effective neutron flux ( including reference 2320100100077 cross section), 2320100100078 (ERR-7) Irradiation, cooling and measuring times. 2320100100079 The uncertainties were assumed to be uncorrelated, 2320100100080 the total uncertainties in the cross section values 2320100100081 could be determined by adding the experimental errors 2320100100082 and the uncertainties of nuclear data into the 2320100100083 quadratic function. 2320100100084 STATUS (COREL,22825001) Data of Sm-144(n,2n)Sm-143m . 2320100100085 HISTORY (20131010C) M.M. 2320100100086 ENDBIB 84 0 2320100100087 COMMON 7 6 2320100100088 ERR-1 ERR-2 ERR-3 ERR-4 ERR-5 ERR-6 2320100100089 ERR-7 2320100100090 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2320100100091 PER-CENT 2320100100092 0.1 0.1 2. 3.0 1. 3.0 2320100100093 0.1 2320100100094 ENDCOMMON 6 0 2320100100095 ENDSUBENT 94 0 2320100199999 SUBENT 23201002 20131010 22372320100200001 BIB 6 12 2320100200002 REACTION (62-SM-144(N,A)60-ND-141-M,,SIG) 2320100200003 DECAY-DATA (60-ND-141-M,62.SEC,DG,756.51,0.91) 2320100200004 656.51+-0.05 keV. 62.+-0.8 sec. 2320100200005 Decay data from J.K.Tuli, Nuclear Wallets Cards(2005) 2320100200006 and R.B.Firestone+, Table of Isotopes: CD-ROM Edition 2320100200007 1.0. John Wiley and Sons Ltd., London(1996). 2320100200008 SAMPLE (62-SM-144,NAT=0.0307) 2320100200009 Isotopic abundance (3.07+-0.07) % . 2320100200010 ADD-RES (COMP) Theoretical calculations by Talys 1.2. 2320100200011 ERR-ANALYS (ERR-HL) Error of half-life value given under 2320100200012 DECAY-DATA . 2320100200013 STATUS (TABLE) Tables I (monitor), IV of J,NSE,174,202,2013. 2320100200014 ENDBIB 12 0 2320100200015 COMMON 1 3 2320100200016 ERR-HL 2320100200017 SEC 2320100200018 0.8 2320100200019 ENDCOMMON 3 0 2320100200020 DATA 5 6 2320100200021 EN EN-ERR DATA ERR-T MONIT 2320100200022 MEV MEV MB MB MB 2320100200023 13.57 0.04 2.7 1.3 76.64 2320100200024 13.75 0.05 3.6 1.2 73.88 2320100200025 14.15 0.07 4.3 1.1 70.32 2320100200026 14.52 0.09 5.0 1.7 67.31 2320100200027 14.75 0.09 6.1 1.8 64.10 2320100200028 14.83 0.10 5.7 1.4 62.56 2320100200029 ENDDATA 8 0 2320100200030 ENDSUBENT 29 0 2320100299999 ENDENTRY 2 0 2320199999999