ENTRY 23239 20140810 22412323900000001 SUBENT 23239001 20140810 22412323900100001 BIB 17 101 2323900100002 TITLE Measurements of isomeric cross sections for the 2323900100003 (n,alpha) reaction on the 142Nd isotope at 2323900100004 approximately 14 MeV neutrons. 2323900100005 AUTHOR (I.A.Reyhancan) 2323900100006 INSTITUTE (2TUKSTU) I.A.Reyhancan 2323900100007 REFERENCE (J,ARI,91,44,2014) Data table. 2323900100008 #doi:10.1016/j.apradiso.2014.05.002 2323900100009 REL-REF (M,,W.W.Givens+,J,NIM,80,95,1970) 2323900100010 (M,23183001,I.A.Reyhancan,J,ARI,70,765,2012) 2323900100011 Cyclic Activation Method (CAM). 2323900100012 (I,,M.Subasi+,J,NSE,135,260,2000) 2323900100013 Fast Sample Transfer System (FSTS). 2323900100014 (R,21807001,A.Pavlik+,J,JP/G,8,1283,1982) 2323900100015 90Zr(n,2n)89Zr c-s data used in ZR/Nb method. 2323900100016 (R,10709001,D.R.Nethaway,J,JIN,40,1285,1978) 2323900100017 93Nb(n,2n)92mNb c-s data used in ZR/Nb method 2323900100018 (M,22787001,V.E.Lewis+,J,NIM,174,141,1980) 2323900100019 Zr/Nb ratio method . 2323900100020 (M,22474001,M.Subasi+,J,NSE,122,(1),423,1996) 2323900100021 FACILITY (LINAC,2TUKCNA) SAMES T-400 Neutron Generator in 2323900100022 combination with a Fast Sample Transfer System (FSTS). 2323900100023 SAMPLE - Dried powder samples of high purity of the natural 2323900100024 Nd2)O(3) (99.99%) were pressed to make four pellets of 2323900100025 13mm diameter, 8.5 mm thickness, about 2 g weight. 2323900100026 The pellets were tightly packed in to thin polyethylene2323900100027 boxes. 2323900100028 - The sample preparation procedure was also applied for2323900100029 the Al(2)O(3 )(99.99%) powders. 2323900100030 All neodymium samples were irradiated and counted for 2323900100031 10 cycles. 2323900100032 INC-SOURCE (D-T) H-3(D,N)He-4 reaction . 2323900100033 300 microA average atomic deuteron beam, 2323900100034 accelerating voltage 250 kV. 2323900100035 METHOD (ACTIV) The angles of the irradiation positions to the2323900100036 deuteron beam were 0, 30, 90, 130 deg, which correspond2323900100037 to the neutron energies 14.83,14.75,14.15,13.57 MeV, 2323900100038 respectively. The effective energies of the incident 2323900100039 neutrons at each sample position were determined by the2323900100040 ratios of 90Zr(n,2n)89Zr (3.27 d) (Pavlik+, 1982) and 2323900100041 93Nb(n,2n)92mNb (10.15 d) (Nethaway, 1978) reaction 2323900100042 cross sections (the Zr/Nb ratio method) (Lewis+, 1980) 2323900100043 and procedure of the energy measurement is given in 2323900100044 detail in Subasi+(1996). 2323900100045 Acrylic plate of 10 mm thickness was placed in front of2323900100046 the detector to protect samples from beta particles 2323900100047 and to minimize the photon absorption and production 2323900100048 bremsstrahlung. 2323900100049 DETECTOR (HPGE) The gamma counting system with a HpGe detector. 2323900100050 Acrylic plate of 10 mm thickness was placed in front of2323900100051 the detector to protect samples from beta particles 2323900100052 and to minimize the photon absorption and production 2323900100053 bremsstrahlung. 2323900100054 (SCIN) During irradiation, the neutron flux was 2323900100055 monitored by the plastic scintillation detector(NE102A)2323900100056 placed under the target, on which the fast neutrons are2323900100057 produced. 2323900100058 MONITOR (13-AL-27(N,A)11-NA-24,,SIG) 2323900100059 Effective flux measured by a calibrated Al foil monitor2323900100060 DECAY-MON (11-NA-24,14.997HR,DG,1368.62,0.9999) 2323900100061 MONIT-REF (,,3,ENDF/B-VII.1,,2011) 2323900100062 ANALYSIS 139mCe (via 142Nd(n,a) ) and 141mNd (via 142Nd(n,2n) ) 2323900100063 radionuclides in the gamma ray spectrum had 2323900100064 754.24+-0.08 keV and 756.51+-0.05 keV gamma lines, 2323900100065 respectively. The search and determination of the photo2323900100066 peaks were performed using the SAMPO90 program. 2323900100067 The calibration spectrum obtained by the standard 2323900100068 sources (60Co, 133Ba, 137Cs, 241Am) was processed to 2323900100069 obtain the proper energy and peak shape calibrations. 2323900100070 The goodness(KHI2) and variance of the fitting 2323900100071 performed for the multiple photo-peaks were 1.0 and 2323900100072 0.3, respectively. 2323900100073 The cross sections were calculated from the cyclic 2323900100074 activation formula. 2323900100075 CORRECTION Dead time and self-absorption corrections - 4%. 2323900100076 The low energy neutron contribution due to scattering 2323900100077 in the target materials reached rates up to 10%. The 2323900100078 effect of low energy neutrons in the sample pellets 2323900100079 packed in thin (1mm thickness) polyethylene boxes was 2323900100080 determined by the MCNP5 Monte Carlo code; rate of less 2323900100081 than 1% was found, which can be neglected. 2323900100082 The attenuation of the gamma rays in the acrylic beta 2323900100083 absorber. 2323900100084 ERR-ANALYS (ERR-T) Total uncertainty (37.5-38.6 %) includes : 2323900100085 (ERR-1) Sample weight, 2323900100086 (ERR-2) Concentration of the element, 2323900100087 (ERR-3) Isotopic abundance, 2323900100088 (ERR-4) Relative gamma-ray intensity, 2323900100089 (ERR-5) Counting solid angle and intrinsic efficiency 2323900100090 of the gamma detector, 2323900100091 (ERR-S,37.2,38.3) Statistical uncertainty (full energy 2323900100092 photo-peak area), 2323900100093 (ERR-6) Neutron flux fluctuation, 2323900100094 (ERR-7) Effective neutron flux ( including reference 2323900100095 cross section), 2323900100096 (ERR-8) Irradiation, cooling and measuring times. 2323900100097 The uncertainties were assumed to be uncorrelated, 2323900100098 the total uncertainties in the cross section values 2323900100099 could be determined by adding the experimental errors 2323900100100 and the uncertainties of nuclear data into the 2323900100101 quadratic function. 2323900100102 HISTORY (20140810C) M.M. 2323900100103 ENDBIB 101 0 2323900100104 COMMON 8 6 2323900100105 ERR-1 ERR-2 ERR-3 ERR-4 ERR-5 ERR-6 2323900100106 ERR-7 ERR-8 2323900100107 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2323900100108 PER-CENT PER-CENT 2323900100109 0.1 0.1 1.8 0.1 3.0 1. 2323900100110 3.0 0.1 2323900100111 ENDCOMMON 6 0 2323900100112 ENDSUBENT 111 0 2323900199999 SUBENT 23239002 20140810 22412323900200001 BIB 7 14 2323900200002 REACTION (60-ND-142(N,A)58-CE-139-M,,SIG) 2323900200003 DECAY-DATA (58-CE-139-M,54.8SEC,DG,754.24,0.92) 2323900200004 SAMPLE (60-ND-142,NAT=0.272) 2323900200005 Isotopic abundance (27.2+-0.5) % . 2323900200006 ADD-RES (COMP) Theoretical calculations by Talys 1.4. 2323900200007 REL-REF (D,12033019,R.G.Wille+,J,PR,118,242,1960) 2323900200008 Value 10+-2 mb is three times different from this work 2323900200009 and the TALYS results. 2323900200010 (O,22825003,I.A.Reyhancan+,J,ANE,30,1539,2003) 2323900200011 Nd-142(N,2N) c-s. 2323900200012 ERR-ANALYS (ERR-HL) Error of half-life value given in DECAY-DATA.2323900200013 (ERR-IDD) Error of gamma intensity value given in 2323900200014 DECAY-DATA . 2323900200015 STATUS (TABLE) Table 1 (monitor), Table 4 of ARI,91,44,2014. 2323900200016 ENDBIB 14 0 2323900200017 COMMON 2 3 2323900200018 ERR-HL ERR-IDD 2323900200019 SEC NO-DIM 2323900200020 0.1 0.0009 2323900200021 ENDCOMMON 3 0 2323900200022 DATA 5 4 2323900200023 EN EN-ERR DATA ERR-T MONIT 2323900200024 MEV MEV MB MB MB 2323900200025 13.57 0.04 1.89 0.71 123.57 2323900200026 14.15 0.07 1.58 0.61 120.55 2323900200027 14.75 0.09 3.2 1.20 112.73 2323900200028 14.83 0.10 2.88 1.09 111.68 2323900200029 ENDDATA 6 0 2323900200030 ENDSUBENT 29 0 2323900299999 ENDENTRY 2 0 2323999999999