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