ENTRY 23255 20150610 22442325500000001 SUBENT 23255001 20150610 22442325500100001 BIB 13 70 2325500100002 REFERENCE (J,NP/A,936,6,2015) 2325500100003 #doi:10.1016/j.nuclphysa.2015.01.003 2325500100004 AUTHOR (N.Dzysiuk, I.Kadenko, V.Gressier, A.J.Koning) 2325500100005 TITLE Cross section measurement of the 159Tb(n,gamma)Tb160 2325500100006 nuclear reaction. 2325500100007 INSTITUTE (2FR FR) V.Gressier . 2325500100008 Institute for Radiation Protection and Nuclear Safety,2325500100009 Cadarache, France. 2325500100010 (4UKRUKR) Int. Nucl. Safety Center of Ukraine, Kyiv. 2325500100011 N.Dzysiuk, I.Kadenko. 2325500100012 (2SWDUPP) N.Dzysiuk . 2325500100013 (2NEDNRG,3ZZZIAE) A.J.Koning . 2325500100014 REL-REF (I,,V.Lacoste,J,RM,45,1250,2010) 2325500100015 Details of long counter. 2325500100016 FACILITY (ACCEL,2FR FR) AMANDE facility (IRSN, Cadarache) based2325500100017 on HVEE 2 MV Tandetron accelerator system. 2325500100018 INC-SOURCE (D-D) Thin deuterated target composed of a Ti layer 2325500100019 saturated by deuterium 825microg/cm2 thick attached to 2325500100020 a 0.5mm thick silver backing. 2325500100021 Characteristics of the deuteron beams: 2325500100022 Neutron energy.MeV 3.7 4.3 5.4 7. 2325500100023 Deuteron beam current,MicroA 5. 8. 13. 2.5 2325500100024 Deuteron beam energy,keV 765. 1234. 2174. 32782325500100025 Mean energy uncertainty,keV 0.8 1. 1.5 2. 2325500100026 FWHM of peak, % 8.6 4.8 2.5 9.2 2325500100027 INC-SPECT Mono-energetic neutrons. 2325500100028 PLC measurements were performed at 5 m and 0deg from 2325500100029 the target both with and without a shadow cone to 2325500100030 measure the fluence of the direct neutrons. The neutron2325500100031 fluence was monitored both by integrating the deuteron 2325500100032 charge deposited on the target and by means of two De 2325500100033 Pangher long counters placed at a distance of 6 m from 2325500100034 the target. 2325500100035 The fluence at the calibration position was determined 2325500100036 with an uncertainty of 2% to 3%. 2325500100037 SAMPLE Metal of natural composition. 2325500100038 Two terbium samples : 2325500100039 - 30mm diameter disk, 5mm of thickness, total mass 2325500100040 28.9g; 2325500100041 - parallelepiped shape, 5x8x10 mm,total mass of 3.3g 2325500100042 METHOD (ACTIV) Terbium samples were irradiated under 0deg 2325500100043 angle with respect to the incoming deuteron beam. 2325500100044 The sample-to-target distance was varied from 3.3cm to 2325500100045 20.3cm leading to neutron fluence rates between 2325500100046 6.E+4 and 3.E+6 /cm2/s . 2325500100047 Volumetric inhomogeneity (i.e. the maximum variation) 2325500100048 in the terbium disk sample was of 39%, 44% and 53% in 2325500100049 fluence and of 54keV, 86keV and 133keV in energy, 2325500100050 respectively at 3.7MeV, 4.3MeV, and 5.4MeV. 2325500100051 The irradiations in the 7MeV neutron field were 2325500100052 performed at three distances: 2325500100053 Distance to the target,cm 15.3 3.3 10.3 2325500100054 Volumetric inhomogeneity,% 14. 93. 22. 2325500100055 Neutron energy error,kev 27. 413. 48. 2325500100056 Counting times between 15 minutes and 17 hours at 2325500100057 1.5cm source-detector distance. 2325500100058 DETECTOR (LONGC) Long counters for reference fluence 2325500100059 verification. 2325500100060 (HPGE) HPGe detector GC1212, CANBERRA for gamma-ray 2325500100061 spectroscopy of samples immediately after irradiation. 2325500100062 The extra-range germanium detector GX4019, CANBERRA at 2325500100063 KINR ( Ukraine) after 5 days . 2325500100064 The energy resolution was found to be 1.9keV for 1332 2325500100065 keV gamma-rays from 60Co ; 0.8keV for 122keV from 57Co.2325500100066 The efficiency calibration of the detector was 2325500100067 performed by 60Co, 137Cs, 152Eu, 241Am sources. 2325500100068 CORRECTION For self-shielding; self-shielding factor 1.02-1.05. 2325500100069 For contribution of low-energy scattered neutrons; 2325500100070 Fractional contribution(FC) 0.30-0.91 . 2325500100071 HISTORY (20150610C) M.M. 2325500100072 ENDBIB 70 0 2325500100073 NOCOMMON 0 0 2325500100074 ENDSUBENT 73 0 2325500199999 SUBENT 23255002 20150610 22442325500200001 BIB 7 28 2325500200002 REACTION (65-TB-159(N,G)65-TB-160,,SIG) 2325500200003 DECAY-DATA (65-TB-160,72.3D,DG,298.58,0.255,DG,966.17,0.252) 2325500200004 ANALYSIS The cross sections were calculated by the isotopic 2325500200005 abundance, the number of nuclei in sample, the decay 2325500200006 constant, the detector efficiency, the gamma yield, 2325500200007 the neutron flux, the times of irradiation, cooling, 2325500200008 measurement, the peak area, the self-shielding factor, 2325500200009 the fractional contribution of the low-energy scattered2325500200010 neutrons - see Eq.(2) of J,NP/A,936,6,2015. 2325500200011 ERR-ANALYS (ERR-T) Total uncertainty combined from individual 2325500200012 uncertainties in quadrature - 7.1 - 38 % . 2325500200013 Sources of uncertainties: 2325500200014 (ERR-S,3.,5.5) Counting rate (3-5.5)% 2325500200015 (ERR-1) Efficiency calibration 2325500200016 (ERR-2,0.22,0.78) Self-absorption of gamma-ray 2325500200017 (ERR-3,,0.1) Constants (mass) <0.1% 2325500200018 (ERR-4,2.3,6.) Neutron flux (2.3-6)% 2325500200019 (ERR-5,0.2,0.7) Gamma intensity (0.2-0.7) 2325500200020 Also self-shielding factor and fractional contribution.2325500200021 Errors of weighting the sample or monitor one are 2325500200022 negligible as well (<0.05%). 2325500200023 REL-REF (R,,R.B.Firestone+,B,FIRESTONE,,1996) 2325500200024 Ref.for HL of Tb-160 2325500200025 (A,12832014,W.P.Poenitz,S,ANL-83-4,239,1982) 2325500200026 (A,30031024,G.Peto+,J,JNE,21,797,1967) 2325500200027 ADD-RES (COMP) Measured data are compared and agree with 2325500200028 TALYS-1.2 calculation . 2325500200029 STATUS (TABLE) Table 3 of J,NP/A,936,6,2015. 2325500200030 ENDBIB 28 0 2325500200031 COMMON 1 3 2325500200032 ERR-1 2325500200033 PER-CENT 2325500200034 3. 2325500200035 ENDCOMMON 3 0 2325500200036 DATA 4 4 2325500200037 EN EN-ERR DATA ERR-T 2325500200038 MEV MEV MB MB 2325500200039 3.6700 0.0008 30.8 2.2 2325500200040 4.2800 0.0010 21.78 1.80 2325500200041 5.3900 0.0015 6.13 0.55 2325500200042 6.850 0.002 2.14 0.83 2325500200043 ENDDATA 6 0 2325500200044 ENDSUBENT 43 0 2325500299999 ENDENTRY 2 0 2325599999999