ENTRY 23300 20160810 22542330000000001 SUBENT 23300001 20160810 22542330000100001 BIB 17 87 2330000100002 AUTHOR (I.A.Reyhancan) 2330000100003 TITLE Cross sections of ground and isomeric states for (n,p) 2330000100004 reaction on Sm-154 between 13.57 and 14.83 MeV neutrons2330000100005 REFERENCE (J,ARI,113,79,2016) 2330000100006 #doi:10.1016/j.apradiso.2016.04.010 2330000100007 INSTITUTE (2TUKSTU) 2330000100008 REL-REF (M,,M.Subasi+,J,NSE,122,(1),423,1996) 2330000100009 Details of method. 2330000100010 (M,,M.Subasi+,J,NSE,130,254,1998) 2330000100011 Details of method. 2330000100012 (M,,M.Subasi+,J,NSE,135,260,2000) 2330000100013 Details of method. 2330000100014 (R,,A.Pavlik+,J,JP/G,8,1283,1982) 2330000100015 90Zr(n,2n)89Zr c-s data used in ZR/Nb method. 2330000100016 (R,,D.R.Nethaway,J,JIN,40,1285,1978) 2330000100017 93Nb(n,2n)92mNb c-s data used in ZR/Nb method. 2330000100018 (M,,V.E.Lewis+,J,NIM,174,141,1980) 2330000100019 Zr/Nb ratio method . 2330000100020 FACILITY (NGEN,2TUKSTU) SAMES T-400 neutron generator with 2330000100021 Fast Sample Transfer System(FSTS), delivering a 2330000100022 sample from irradiation position to HPGe detector 2330000100023 within 0.5 sec. 2330000100024 Beam current is kept at about 300 microA with 2330000100025 accelerator voltage of 250 kV. 2330000100026 INC-SOURCE (D-T) Deuteron beam current 350 microA. 2330000100027 The irradiation positions at the angles to the deuteron2330000100028 beam were 0, 30, 60, 90, 120, corresponding to the 2330000100029 neutron energies 14.83, 14.75, 14.52, 14.15, 13.75 MeV.2330000100030 INC-SPECT The effective energy of incident neutron at each 2330000100031 irradiation position were determined by the ratio of 2330000100032 90Zr(n,2n)89Zr (3.27 d) (Pavlik+,1982) 2330000100033 and 93Nb(n,2n)92mNb (10.15 d) (Nethaway,1978) reaction 2330000100034 cross sections (the Zr/Nb ratio method) (Lewis and 2330000100035 Zieba, 1980) and are given in detail in Subasi+,1996. 2330000100036 Neutron fluxes are measured in each irradiation place 2330000100037 (70mm from the neutron source )from 7.0+7 to 1.0E+ 2330000100038 n/cm2*s, depending on the neutron target condition. 2330000100039 MONITOR (13-AL-27(N,P)12-MG-27,,SIG) 2330000100040 DECAY-MON (12-MG-27,9.458MIN,DG,843.8,0.073) 2330000100041 MONIT-REF (,,3,ENDF/B-VII.1,,2015) 2330000100042 SAMPLE Sample pellets(13mm diameter,8.5mm thickness, about 2g2330000100043 weight) were pressed from the high-purity (99.9%) Sm2O32330000100044 and Al2O3 powders. Water contents were removed by 2330000100045 heating up to 105 deg C, then 0.5h cooled down to the 2330000100046 room temperature, were filled in dry stainless steel 2330000100047 capsules, pressed to form a dense pellet, were tightly 2330000100048 packed into thin polyethylene(PE) boxes and sealed-of. 2330000100049 METHOD (ACTIV) Cyclic irradiation. 10 cycles. 2330000100050 Al standard sample irradiation - 30 min. 2330000100051 DETECTOR (SCIN) During irradiation of Al, the neutron flux was 2330000100052 monitored with plastic scintillation detector NE102A, 2330000100053 placed under the neutron-producing target. The monitor 2330000100054 was calibrated with the standard reaction irradiating 2330000100055 Al2O3 sample placed in the same irradiation position. 2330000100056 During irradiation of Sm, the neutrons were monitored 2330000100057 by NE102E detector (MCS mode). 2330000100058 (HPGE) HPGe Detector (Canberra, 82 cm3, 1.79 keV(FWHM) 2330000100059 resolution at 1.333 MeV) at 160 mm from detector - to 2330000100060 measure gamma activities induced in Al and Sm samples.2330000100061 An acrylic plate of 10 mm thickness was placed in front2330000100062 of the detector in order to eliminate the beta-gamma 2330000100063 summing effect. 2330000100064 The total efficiency was determined using the 2330000100065 single-line nuclides of 241Am (60 keV), 109Cd (88 keV),2330000100066 57Co (122+136 keV), 137Cs (662 keV), 54Mn (835 keV), 2330000100067 60Co (1173+1332 keV) with 3% error. 2330000100068 PART-DET (DG) Decay gamma-rays. 2330000100069 CORRECTION For dead time and the self-absorption of the gamma ray 2330000100070 in the pellet(4%). 2330000100071 Neutron flux was corrected for the neutron flux 2330000100072 variations. 2330000100073 The effects of coincidence summing and random 2330000100074 coincidences were neglected because the measurements 2330000100075 were carried out at a long distance 160 mm from the 2330000100076 detector. 2330000100077 For the self-absorption of gamma rays in the sample 2330000100078 and monitor as well as the beta absorber; gamma-ray 2330000100079 attenuations determined experimentally were found to be2330000100080 up to 1% and 2% for all the pellets and the beta 2330000100081 absorber, respectively. 2330000100082 For low energy neutron contribution to the investigated2330000100083 reactions - up to 10% of the total neutron spectrum. 2330000100084 The effect of low energy neutron in sample pellets 2330000100085 packed in thin polyethylene boxes was performed by the 2330000100086 MCNP5 Monte Carlo code (X-5MonteCarloTeam,2003) and 2330000100087 found less than 1% that can be neglected. 2330000100088 HISTORY (20160810C) M.M. 2330000100089 ENDBIB 87 0 2330000100090 NOCOMMON 0 0 2330000100091 ENDSUBENT 90 0 2330000199999 SUBENT 23300002 20160810 22542330000200001 BIB 9 50 2330000200002 REACTION 1(62-SM-154(N,P)61-PM-154-G,,SIG) 2330000200003 2(62-SM-154(N,P)61-PM-154-M,,SIG) 2330000200004 SAMPLE Isotopic abundance 22.75+-0.29 % 2330000200005 COMMENT Of compiler, confirmed by the author 10.08.2016. 2330000200006 In the article Table 2 there is an misprint in 2330000200007 isotopic abundance: 75.+-0.29 -> 22.75+-0.29. 2330000200008 REL-REF (R,,C.W.Reich,J,NDS,110,2257,2009) HL and spins. 2330000200009 (A,31439004,A.Kirov+,J,ZP/A,345,(3),285,1993) 2330000200010 Reasonable agreement. 2330000200011 (N,12033031,R.G.Wille+,J,PR,118,242,1960) 2330000200012 3.5+-0.2 mb - total n,p cross section. 2330000200013 DECAY-DATA1(61-PM-154-G,2.68MIN,DG,184.8,0.32) 2330000200014 2.68+-0.07 min 2330000200015 2(61-PM-154-M,1.73MIN,DG,1393.58,0.144) 2330000200016 1.73+-0.10 min 2330000200017 Decay data from NuDat2.6, 2015 and from REL-REF of 2330000200018 Reich 2330000200019 ANALYSIS Full energy peak (FEP) area, mass of sample, 2330000200020 the concentration of the element, Avogadro number,the 2330000200021 atomic weight of the element, isotopic abundance, the 2330000200022 relative gamma-ray intensity, effective flux measured 2330000200023 by calibrated Al foil monitor, counting solid angle 2330000200024 with self-absorption correction, FEP efficiency of the 2330000200025 gamma-ray detector, decay constant, the number of 2330000200026 cycles were used to cross-section calculation by the 2330000200027 cyclic activation formula using the one-cycle time as 2330000200028 sum of irradiation, delay, counting, return times. 2330000200029 ERR-ANALYS (ERR-T) Total uncertainty. 2330000200030 Sources of uncertainty: 2330000200031 (ERR-1) Sample weight. 2330000200032 (ERR-2) Concentration of the element. 2330000200033 (ERR-3) Isotopic abundance. 2330000200034 (ERR-4) Counting solid angle and 2330000200035 intrinsic efficiency of the gamma detector. 2330000200036 (ERR-S) Statistical uncertainty ( full energy 2330000200037 photo-peak area). 2330000200038 (ERR-5) Neutron flux fluctuation. 2330000200039 (ERR-6) Effective neutron flux 2330000200040 (reference cross-section). 2330000200041 (ERR-7,0.,4.0) Coincidence summing 2330000200042 (ERR-8) irradiation, cooling and measuring times. 2330000200043 Uncertainties were assumed to be uncorrelated. 2330000200044 The total uncertainty could be determined by adding the2330000200045 experimental errors and the uncertainties of nuclear 2330000200046 data in the quadratic form. 2330000200047 ADD-RES (COMP) Compared with statistical model calculations by 2330000200048 the code TALYS. 2330000200049 STATUS (TABLE) Table 1(monitor), Table 2( decay data), 2330000200050 Table 3 (uncertainties), Table 4(cross sections) of 2330000200051 J,ARI,113,79,2016 . 2330000200052 ENDBIB 50 0 2330000200053 COMMON 8 6 2330000200054 ERR-1 ERR-2 ERR-3 ERR-4 ERR-S ERR-5 2330000200055 ERR-6 ERR-8 2330000200056 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2330000200057 PER-CENT PER-CENT 2330000200058 0.1 0.1 1.3 3.0 15. 1. 2330000200059 3.0 0.1 2330000200060 ENDCOMMON 6 0 2330000200061 DATA 7 5 2330000200062 EN EN-ERR DATA 1ERR-T 1DATA 2ERR-T 22330000200063 MONIT 2330000200064 MEV MEV MB MB MB MB 2330000200065 MB 2330000200066 13.75 0.05 0.36 0.06 2330000200067 73.88 2330000200068 14.15 0.07 0.79 0.12 2330000200069 70.32 2330000200070 14.52 0.09 1.4 0.22 2330000200071 67.31 2330000200072 14.75 0.09 1.67 0.26 0.64 0.1 2330000200073 64.10 2330000200074 14.83 0.10 1.85 0.29 0.82 0.13 2330000200075 62.56 2330000200076 ENDDATA 14 0 2330000200077 ENDSUBENT 76 0 2330000299999 ENDENTRY 2 0 2330099999999