ENTRY 23160 20120801 22332316000000001 SUBENT 23160001 20120801 22332316000100001 BIB 17 88 2316000100002 TITLE Measurements and model calculations of isomeric 2316000100003 cross-sections for (n,alpha) reaction on 140-Ce isotope2316000100004 around 14 MeV neutrons. 2316000100005 AUTHOR (I.A.Reyhancan) 2316000100006 INSTITUTE (2TUKCNA) Cekmece Nuclear Research and Training Center.2316000100007 (2TUKSTU) Istanbul Technical University, Institute of 2316000100008 Energy, Ayazaga Campus, Maslak 34469, Istanbul, Turkey.2316000100009 REFERENCE (J,ANE,47,81,2012) Data table. 2316000100010 #doi:10.1016/j.anucene.2012.04.009 2316000100011 REL-REF (R,21807001,A.Pavlik+,J,JP/G,8,1283,1982) 2316000100012 90Zr(n,2n)89Zr c-s data used in ZR/Nb method. 2316000100013 (R,10709001,D.R.Nethaway,J,JIN,40,1285,1978) 2316000100014 93Nb(n,2n)92mNb c-s data used in ZR/Nb method. 2316000100015 (M,,V.E.Lewis,J,NIM,174,141,1980) 2316000100016 Zr/Nb ratio method . 2316000100017 (M,22474001,M.Subasi+,J,NSE,122,(1),423,1996) 2316000100018 Details of Zr/Nb method. 2316000100019 FACILITY (LINAC,2TUKCNA) SAMES T-400 Neutron Generator in 2316000100020 combination with a Fast Sample Transfer System (FSTS), 2316000100021 deliver the sample from the irradiation position to 2316000100022 HpGe detector or vice versa within 0.5 s. 2316000100023 INC-SOURCE (D-T) H-3(D,N)He-4 reaction 2316000100024 INC-SPECT At the irradiation place (70 mm from neutron source), 2316000100025 neutron fluxes are ranged from 0.9E+7 and 1.6E+7 2316000100026 n/cm2/s, depending on the neutron target condition. 2316000100027 METHOD (ACTIV) Five different positions around the target 2316000100028 holder inclined at 45 deg were used. The angles of 2316000100029 the irradiation positions along the deuteron beam were 2316000100030 0, 30, 60, 120, 130 deg,which correspond to the neutron2316000100031 energies 14.83, 14.75, 14.52, 13.75, 13.57 MeV, 2316000100032 respectively. The effective energies of the incident 2316000100033 neutrons at each sample position were determined by the2316000100034 ratio of 90Zr(n,2n)89Zr (3.27 d) (Pavlik+, 1982) and 2316000100035 93Nb(n,2n)92mNb (10.15 d) (Nethaway, 1978) reaction 2316000100036 cross sections (the Zr/Nb ratio method) (Lewis+, 1980) 2316000100037 and were given in detail in Subasi+(1996). 2316000100038 Acrylic plate of 10 mm thickness was placed in front of2316000100039 the detector to block the beta particles from samples 2316000100040 and to minimize the photon absorption and production of2316000100041 bremsstrahlung. 2316000100042 DETECTOR (HPGE) Gamma counting system with HpGe detector 2316000100043 (Canberra, 82 cm3, 1.79 keV FWHM at 1333 keV), see 2316000100044 REL-REF of Subasi+,1996. 2316000100045 (SCIN) NE102A scintillation detector for neutron flux 2316000100046 determination using of Al2-O3 and Al monitor samples. 2316000100047 High-resolution gamma-ray spectrometer was used to 2316000100048 measure gamma activity induced in the Al pellet. 2316000100049 MONITOR (13-AL-27(N,P)12-MG-27,,SIG) 2316000100050 DECAY-MON (12-MG-27,9.458MIN,DG,843.8,0.73) 2316000100051 MONIT-REF (,,3,ENDF/B-VII.0,,2006) Evaluated by M.Wagner+, 2316000100052 1990, Physics Data. vol. 13 (5), 1990, 2316000100053 and adopted for ENDF/B-VII.0. 2316000100054 SAMPLE Sample pellets of 13 mm diameter, 8.5 mm thickness, 2316000100055 about 2 g weight were pressed from the natural, 2316000100056 high-purity (99.9%) Ce2O3, and Al2O3 powders. 2316000100057 Water contents in the samples were removed by heating 2316000100058 the oxide materials up to 105 deg C, then they were 2316000100059 kept in a desiccator for 0.5 h to cool down to the room2316000100060 temperature; after that, they were filled in dry 2316000100061 stainless steel capsules and pressed to form a dense 2316000100062 pellet; the pellets were tightly packed into thin 2316000100063 polyethylene boxes and sealed-off. 2316000100064 CORRECTION Self-absorption corrections are obtained from solid 2316000100065 angle calculation with absorption as 4%, 7% for gamma 2316000100066 rays of irradiated Al and Ce samples respectively. 2316000100067 Attenuation of the gamma rays in a beta absorber. 2316000100068 Random coincidences of the gamma peaks. 2316000100069 Dead time. 2316000100070 Fluctuations of the neutron flux during irradiation. 2316000100071 Contributions from low energy neutrons (about 5%). 2316000100072 ERR-ANALYS (ERR-T) Total error includes errors due to: 2316000100073 (ERR-1) Sample weight, 2316000100074 (ERR-2) Concentration of the element, 2316000100075 (ERR-3) Isotopic abundance, 2316000100076 (ERR-4) Counting solid angle and intrinsic efficiency 2316000100077 of the gamma detector, 2316000100078 (ERR-S,22.,41.) Statistical uncertainty (full energy 2316000100079 photo-peak area), 2316000100080 (ERR-5) Neutron flux fluctuation, 2316000100081 (ERR-6) Effective neutron flux ( including reference 2316000100082 cross section), 2316000100083 (ERR-7) Irradiation, cooling and measuring times. 2316000100084 The uncertainties were assumed to be uncorrelated, so 2316000100085 the total uncertainties in the cross section values 2316000100086 could be determined by adding the experimental errors 2316000100087 and the uncertainties of nuclear data in the quadratic 2316000100088 form. 2316000100089 HISTORY (20120801C) M.M. 2316000100090 ENDBIB 88 0 2316000100091 COMMON 7 6 2316000100092 ERR-1 ERR-2 ERR-3 ERR-4 ERR-5 ERR-6 2316000100093 ERR-7 2316000100094 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2316000100095 PER-CENT 2316000100096 0.1 0.1 0.02 3.0 1. 3.0 2316000100097 0.1 2316000100098 ENDCOMMON 6 0 2316000100099 ENDSUBENT 98 0 2316000199999 SUBENT 23160002 20120801 22332316000200001 BIB 7 20 2316000200002 REACTION (58-CE-140(N,A)56-BA-137-M,,SIG) 2316000200003 DECAY-DATA (56-BA-137-M,2.552MIN,DG,661.659,0.9011) 2316000200004 661.659+-0.003 keV. 2316000200005 Decay data from J.K.Tuli, Nuclear Wallets Cards(2005) 2316000200006 and R.B.Firestone+, Table of Isotopes: CD-ROM Edition 2316000200007 1.0. John Wiley and Sons Ltd., London(1996). 2316000200008 SAMPLE (58-CE-140,NAT=0.88450) 2316000200009 Isotopic abundance (88.450+-0.0018) % . 2316000200010 ADD-RES (COMP) Theoretical calculations by Talys 1.2. 2316000200011 REL-REF (D,20900005,M.Bormann+,R,EANDC(E)-66,42,1966) 2316000200012 (D,22365009,Y.Satoh+,R,JAERI-95-008,189,1995) 2316000200013 Slightly higher. 2316000200014 (D,22311007,S.Murahira+,R,INDC(JPN)-175/U,171,1995) 2316000200015 Slightly higher. 2316000200016 (A,22393004,Y.Kasugai+,C,97TRIEST,1,635,1997) Agree. 2316000200017 ERR-ANALYS (ERR-HL) Error of half-life value given under 2316000200018 DECAY-DATA . 2316000200019 (ERR-IDD) Error of intensity value given under 2316000200020 DECAY-DATA . 2316000200021 STATUS (TABLE) Tables 1 (monitor c-s), 4 of J,ANE,47,81,2012. 2316000200022 ENDBIB 20 0 2316000200023 COMMON 2 3 2316000200024 ERR-HL ERR-IDD 2316000200025 MIN NO-DIM 2316000200026 0.001 0.0006 2316000200027 ENDCOMMON 3 0 2316000200028 DATA 5 5 2316000200029 EN EN-ERR DATA ERR-T MONIT 2316000200030 MEV MEV MB MB MB 2316000200031 13.57 0.04 1.42 0.59 76.64 2316000200032 13.75 0.05 1.48 0.47 73.88 2316000200033 14.52 0.09 1.48 0.51 67.31 2316000200034 14.75 0.09 1.93 0.55 64.10 2316000200035 14.83 0.10 2.05 0.45 62.56 2316000200036 ENDDATA 7 0 2316000200037 ENDSUBENT 36 0 2316000299999 ENDENTRY 2 0 2316099999999