ENTRY 22877 20090914 2287700000001
SUBENT 22877001 20090914 20100416 2287700100001
BIB 15 98 2287700100002
TITLE New cross section measurements for neutron-induced 2287700100003
reactions on Cr,Ni,Cu,Ta and W isotopes obtained with 2287700100004
the activation technique. 2287700100005
AUTHOR (V.Semkova, R.Capote, R.J.Tornin, A.J.Koning, A.Moens, 2287700100006
A.J.M.Plompen) 2287700100007
INSTITUTE (2ZZZGEL) V.Semkova,R.J.Tornin,A.Moens,A.J.M.Plompen 2287700100008
(3BULBLA) V.Semkova - Institute for Nuclear Research 2287700100009
and Nuclear Energy,Bulgaria 2287700100010
(2NEDNRG) A.J.Koning -Nuclear Research and Consultancy2287700100011
Group, Petten,Netherlands 2287700100012
(3ZZZIAE) R.Capote -Nuclear Data Section, IAEA. 2287700100013
REFERENCE (C,2007NICE,1,559,200704) Graphs. 2287700100014
#doi:10.1051/ndata:07320 2287700100015
(C,2008VILLIG,,75,200810) Graphs for data of reactions 2287700100016
of Subents 003, 004,011,006,009,015 . 2287700100017
(S,EUR-22794,117,2007) Graphs. 2287700100018
Proc.of the NEMEA-III Workshop 25-28 Oct.2006, 2287700100019
Borovets,Bulgaria, edited by A.J.M.Plompen. 2287700100020
A,2007NICE,62(#320),200704 -Abstract. 2287700100021
REL-REF (I,22820001,V.Semkova+,J,NP/A,730,255,2004) Detail 2287700100022
description of measurement technique.2287700100023
#doi:10.1016/j.nuclphysa.2003.11.005 2287700100024
NSR=2004SE01 2287700100025
FACILITY (VDG,2ZZZGEL)) 7-MV Van de Graaff accelerator at IRMM, 2287700100026
Geel. 2287700100027
INC-SOURCE (D-T) 1-H-3(d,n)2-He-4. Deuterons energy 1,2,3,4 MeV. 2287700100028
Distance between the sample stack and the center of 2287700100029
target varied from 3cm for samples of 10mm diameter to2287700100030
7cm for samples of 30mm diameter. 2287700100031
Ti/T target of 2mg/cm**2 thickness on silver backing 2287700100032
of 0.4mm thickness. 2287700100033
INC-SPECT Quasi-monoenergetic neutrons of energy from 13.8 to 2287700100034
20.5 MeV. 2287700100035
METHOD (ACTIV) Activation method in combination with gamma- 2287700100036
(GSPEC) spectrometry. 2287700100037
Radioactivity of samples was measured by standard 2287700100038
gamma-ray spectrometry. 2287700100039
MONITOR (13-AL-27(N,A)11-NA-24,,SIG) Standard cross section of 2287700100040
ENDF/B-VI - for neutron fluence rate determination. 2287700100041
Used as secondary standards in spectral index method: 2287700100042
(13-AL-27(N,P)12-MG-27,,SIG) 2287700100043
(26-FE-56(N,P)25-MN-56,,SIG) 2287700100044
(28-NI-58(N,P)27-CO-58,,SIG) 2287700100045
(41-NB-93(N,2N)41-NB-92-M,,SIG) 2287700100046
(49-IN-115(N,INL)49-IN-115-M,,SIG) 2287700100047
SAMPLE Each sample were sandwiched between monitor foils and 2287700100048
placed at angles between 0 deg and 75 deg relative to 2287700100049
incident deuteron beam. 2287700100050
DETECTOR (HPGE) Coaxial HPGe detector.In addition to standard 2287700100051
detector efficiency calibration a Monte Carlo 2287700100052
simulation was performed with MCNP5 code to achieve 2287700100053
higher geometry flexibility and better accuracy. 2287700100054
Full-energy peak and total efficiencies for detector 2287700100055
measuring geometry were calculated by MCNP5 code for 2287700100056
large Cr,Ni,Cu,Ta samples and for W samples due to 2287700100057
high gamma-ray attenuation.To increase counting 2287700100058
statistics, stack of several W samples were irradiated,2287700100059
and spread on detector cap to avoid counting loss due 2287700100060
to gamma-ray absorption. 2287700100061
Standard point sources were used for : 2287700100062
-detector efficiency calibration (fitting of experimen.2287700100063
values with empirical functions provides accuracy of 2287700100064
2.5 to 5 % for conventionally used sample geometry), 2287700100065
-absolute detector 2287700100066
efficiency measurement by variation of source-to- 2287700100067
detector positions. 2287700100068
(LONGC) Long-counter operated in multichannel-scaling 2287700100069
acquisition mode to record the time profile of neutron 2287700100070
flux during irradiation. 2287700100071
CORRECTION Coincidence summing correction in the case of V-48, 2287700100072
Co-56,Fe-59,Lu-178m,Lu-178g,Hf-180m,Hf-181,Ta-182, 2287700100073
Ta-183,Ta-184, Hf-183,Ta-185,Ta-186,W-185m activities 2287700100074
measurement. 2287700100075
Measured gamma-ray count rates were corrected for: 2287700100076
gamma-ray abundance, 2287700100077
gamma-ray self-absorption, 2287700100078
efficiency of detector, 2287700100079
irradiation and measurement geometry, 2287700100080
neutron flux fluctuation during irradiation. 2287700100081
secondary neutrons. 2287700100082
Also corrections in data analysis: 2287700100083
- dead time effects, 2287700100084
- low energy neutron background, 2287700100085
- neutron flux and energy distribution inside the 2287700100086
stack of sample and monitor foils. 2287700100087
STATUS (UNOBT) E-mails were sent to the corresponding author 2287700100088
A.Plompen with request for data 10 Dec.2007, 2287700100089
09 Oct. 2008. 2287700100090
Reply - data are not ready for EXFOR data base. 2287700100091
Request for te data of C,2008VILLIG was sent 2287700100092
07.07.2009 . 2287700100093
(COREL,22822003) For data for Zr-90(n,p)Y-90m of 2287700100094
C,2008VILLIG see Entry 22822 Subent 003. 2287700100095
(COREL,22822005) For data for Zr-91(n,x)Y-90m of 2287700100096
C,2008VILLIG see Entry 22822 Subent 005. 2287700100097
HISTORY (20081015C) M.M. 2287700100098
(20090914A) M.M. Reference C,2008VILLIG was added. 2287700100099
Request for the newer data was sent to A.Plompen. 2287700100100
ENDBIB 98 0 2287700100101
NOCOMMON 0 0 2287700100102
ENDSUBENT 101 0 2287700199999
SUBENT 22877002 20090914 20100416 2287700200001
BIB 5 13 2287700200002
REACTION (24-CR-50(N,X)23-V-48,,SIG) 2287700200003
SAMPLE Disc-shaped high-purity natural chromium of 30 mm 2287700200004
diameter, 5mm thickness. Nominal weight 25500mg. 2287700200005
DECAY-DATA (23-V-48,15.9735D,DG,983.525,0.9989) 2287700200006
ANALYSIS Decay parameters applied in data analysis were taken 2287700200007
from ENSDF data base. 2287700200008
Threshold of reactions, which contribute to V-48 2287700200009
production from Cr-50 are 12.9 MeV for (n,t), 19.3 MeV2287700200010
for (n,nd), 21.6 MeV for (n,2np). So, Cr-50(n,x)V-48 2287700200011
reaction cross-section can be considered as pure (n,t)2287700200012
reaction in investigated energy range. 2287700200013
STATUS Fig.1 top left of C,2007NICE,1,559,200704 . 2287700200014
Fig.1 top left of R,EUR-22794,117,2007. 2287700200015
ENDBIB 13 0 2287700200016
NOCOMMON 0 0 2287700200017
NODATA 0 0 2287700200018
ENDSUBENT 17 0 2287700299999
SUBENT 22877003 20090914 20100416 2287700300001
BIB 6 17 2287700300002
REACTION (28-NI-58(N,P+A)25-MN-54,,SIG) 2287700300003
SAMPLE Disc-shaped high-purity natural nickel of 14 mm 2287700300004
diameter, 5mm thickness. Nominal weight 5000 mg. 2287700300005
Mn impurity in sample - 100 ppm. 2287700300006
Fe impurity - 40 ppm. 2287700300007
DECAY-DATA (25-MN-54,312.12D,DG,834.848,0.99976) 2287700300008
ANALYSIS Decay parameters applied in data analysis were taken 2287700300009
from ENSDF data base. 2287700300010
Contribution from Mn-55(n,2n)Mn-54 reaction(less 1%.),2287700300011
contribution from Fe-54(n,p)Mn-54 reaction (less 0.1%)2287700300012
were estimated on the base of impurity in sample and 2287700300013
assumed cross-sections, respectively . 2287700300014
ASSUMED (ASSUM1,25-MN-55(N,2N)25-MN-54,,SIG) 2287700300015
(ASSUM2,26-FE-54(N,P)25-MN-54,,SIG) 2287700300016
STATUS Fig.1 top right of C,2007NICE,1,559,200704 . 2287700300017
Fig.1 top right of R,EUR-22794,117,2007. 2287700300018
Fig.1 top right of C,2008VILLIG,75,200810. 2287700300019
ENDBIB 17 0 2287700300020
COMMON 2 3 2287700300021
ASSUM1 ASSUM2 2287700300022
MB MB 2287700300023
800. 200. 2287700300024
ENDCOMMON 3 0 2287700300025
NODATA 0 0 2287700300026
ENDSUBENT 25 0 2287700399999
SUBENT 22877004 20090914 20100416 2287700400001
BIB 5 12 2287700400002
REACTION (28-NI-58(N,X)27-CO-56,,SIG) 2287700400003
SAMPLE Disc-shaped high-purity natural nickel of 14 mm 2287700400004
diameter, 5mm thickness. 2287700400005
DECAY-DATA (27-CO-56,77.233D,DG,846.771,0.99935) 2287700400006
ANALYSIS Decay parameters applied in data analysis were taken 2287700400007
from ENSDF data base. 2287700400008
Potential interference from Ni-58(n,3n) ad Ni-58(n,3p)2287700400009
were discarded because threshold of 1st one -22.9 MeV,2287700400010
low contribution from 2nd reaction due to Coulomb 2287700400011
barrier. 2287700400012
STATUS Fig. 1 bottom left of C,2007NICE,1,559,200704.2287700400013
Fig. 1 top left of C,2008VILLIG,75,200810. 2287700400014
ENDBIB 12 0 2287700400015
NOCOMMON 0 0 2287700400016
NODATA 0 0 2287700400017
ENDSUBENT 16 0 2287700499999
SUBENT 22877005 20090914 20100416 2287700500001
BIB 5 15 2287700500002
REACTION (29-CU-63(N,P+A)26-FE-59,,SIG) 2287700500003
SAMPLE Disc-shaped high-purity natural copper of 20 mm 2287700500004
diameter, 5mm thickness. Nominal weight 14000 mg. 2287700500005
DECAY-DATA (26-FE-59,44.495D,DG,1099.245,0.565, 2287700500006
DG,1291.590,0.432) 2287700500007
ANALYSIS Decay parameters applied in data analysis were taken 2287700500008
from ENSDF data base. 2287700500009
Impurities of Fe,Co,Ni in the Cu sample can contribute2287700500010
to production of Fe-59 by Fe-58(n,g)Fe-59, 2287700500011
Co-59(n,p)Fe-59, Ni-62(n,a)Fe-59 reactions. However, 2287700500012
there were no traces found from activities produced by2287700500013
other high cross section reactions on the above 2287700500014
mentioned elements in the measured spectra. 2287700500015
STATUS Fig. 1 bottom right of C,2007NICE,1,559,200704 .2287700500016
Fig.1 bottom right of R,EUR-22794,117,2007. 2287700500017
ENDBIB 15 0 2287700500018
NOCOMMON 0 0 2287700500019
NODATA 0 0 2287700500020
ENDSUBENT 19 0 2287700599999
SUBENT 22877006 20090914 20100416 2287700600001
BIB 5 8 2287700600002
REACTION (73-TA-181(N,A)71-LU-178-M,,SIG) 2287700600003
SAMPLE Disc-shaped high-purity natural tantalum of 15 mm 2287700600004
diameter, 1mm thickness.Nominal weight 2900mg. 2287700600005
DECAY-DATA (71-LU-178-M,23.1MIN,DG,426.36,0.970) 2287700600006
ANALYSIS Decay parameters applied in data analysis were taken 2287700600007
from ENSDF data base. 2287700600008
STATUS Fig. 2 top left of C,2007NICE,1,559,200704 . 2287700600009
Fig.2 top right of R,EUR-22794,117,2007. 2287700600010
ENDBIB 8 0 2287700600011
NOCOMMON 0 0 2287700600012
NODATA 0 0 2287700600013
ENDSUBENT 12 0 2287700699999
SUBENT 22877007 20090914 20100416 2287700700001
BIB 5 8 2287700700002
REACTION (73-TA-181(N,A)71-LU-178-G,,SIG) 2287700700003
SAMPLE Disc-shaped high-purity natural tantalum of 15 mm 2287700700004
diameter, 1mm thickness. Nominal weight 2900 mg. 2287700700005
DECAY-DATA (71-LU-178-G,28.4MIN,DG,1340.8,0.0342) 2287700700006
ANALYSIS Decay parameters applied in data analysis were taken 2287700700007
from ENSDF data base. 2287700700008
STATUS Fig. 2 bottom left of C,2007NICE,1,559,200704 . 2287700700009
Fig.2 top middle, right of R,EUR-22794,117,2007.2287700700010
ENDBIB 8 0 2287700700011
NOCOMMON 0 0 2287700700012
NODATA 0 0 2287700700013
ENDSUBENT 12 0 2287700799999
SUBENT 22877008 20090914 20100416 2287700800001
BIB 5 9 2287700800002
REACTION (73-TA-181(N,P)72-HF-181,,SIG) 2287700800003
SAMPLE Disc-shaped high-purity natural tantalum of 13 mm 2287700800004
diameter, 0.1mm thickness. Nominal weight 222 mg. 2287700800005
DECAY-DATA (72-HF-181,42.39D,DG,482.10,0.805) 2287700800006
ANALYSIS Decay parameters applied in data analysis were taken 2287700800007
from ENSDF data base. 2287700800008
STATUS Fig. 2 top right of C,2007NICE,1,559,200704 . 2287700800009
Fig.2 top middle, left of R,EUR-22794,117,2007. 2287700800010
Fig.1 bottom left of C,2008VILLIG,75,200810, newer data2287700800011
ENDBIB 9 0 2287700800012
NOCOMMON 0 0 2287700800013
NODATA 0 0 2287700800014
ENDSUBENT 13 0 2287700899999
SUBENT 22877009 20090914 20100416 2287700900001
BIB 5 12 2287700900002
REACTION (73-TA-181(N,X)72-HF-180-M,,SIG) 2287700900003
SAMPLE Disc-shaped high-purity natural tantalum of 13 mm 2287700900004
diameter, 0.1mm thickness. Nominal weight 222 mg. 2287700900005
DECAY-DATA (72-HF-180-M,5.5HR,DG,332.275,0.941) 2287700900006
ANALYSIS Decay parameters applied in data analysis were taken 2287700900007
from ENSDF data base. 2287700900008
STATUS Fig. 2 bottom right of C,2007NICE,1,559,200704 . 2287700900009
Fig.2 bottom middle,left of R,EUR-22794,117,2007.2287700900010
In C,2008VILLIG,75,200810, this reaction data were 2287700900011
discussed, but the graph is not presented (there is a 2287700900012
mistake in Fig.1 - data of W-183(n,x)Ta-182 were 2287700900013
presented twice). 2287700900014
ENDBIB 12 0 2287700900015
NOCOMMON 0 0 2287700900016
NODATA 0 0 2287700900017
ENDSUBENT 16 0 2287700999999
SUBENT 22877010 20090914 20100416 2287701000001
BIB 5 14 2287701000002
REACTION (73-TA-181(N,2N)73-TA-180-G,,SIG) 2287701000003
SAMPLE Disc-shaped high-purity natural tantalum of 13 mm 2287701000004
diameter, 0.1mm thickness. Nominal weight 222 mg. 2287701000005
DECAY-DATA (73-TA-180-G,8.154HR,DG,93.4,0.0451) 2287701000006
ANALYSIS Decay parameters applied in data analysis were taken 2287701000007
from ENSDF data base. 2287701000008
Contribution of 181-Ta(n,x)Hf-180m reaction 2287701000009
(Hf-180m emits 93.325 keV gamma-ray with 17.1% 2287701000010
emission probability)to 93.4 keV gamma-line was found 2287701000011
to be negligible in comparison with 2287701000012
Ta-181(n,2n)Ta-180g reaction based on measurement of 2287701000013
the decay curve. 2287701000014
STATUS Fig. 3 of C,2007NICE,1,559,200704 . 2287701000015
Fig.2 top left of R,EUR-22794,117,2007. 2287701000016
ENDBIB 14 0 2287701000017
NOCOMMON 0 0 2287701000018
NODATA 0 0 2287701000019
ENDSUBENT 18 0 2287701099999
SUBENT 22877011 20090914 20100416 2287701100001
BIB 5 25 2287701100002
REACTION (74-W-182(N,P)73-TA-182,,SIG) 2287701100003
SAMPLE Natural tungsten samples were prepared by either 2287701100004
punching discs of 13mm diameter or by cutting squares 2287701100005
of 1 cm**2 from metallic foil.Depending on energy of 2287701100006
measured gamma-rays,samples of 0.1 or 0.25mm thickness2287701100007
were used to minimize gamma-ray attenuation. 2287701100008
Isotopic composition: W-180 - (0.12+-0.01)%, 2287701100009
W-182 - (26.50+-0.16)%, W-183 - (14.34+-0.04)%, 2287701100010
W-184 - (30.64+-0.02)%, W-186 - (28.43+-0.19)%. 2287701100011
The enriched W-182 sample was prepared from metal 2287701100012
powder canned in plexiglass container. Isotopic 2287701100013
composition: W-180 < 0.03, W-182 - 91.6%, 2287701100014
W-183 - 5.03%, W-184 - 2.46%, W-186 - 0.91%. 2287701100015
DECAY-DATA (73-TA-182,114.43D,DG,1221.4,0.270) 2287701100016
ANALYSIS Decay parameters applied in data analysis were taken 2287701100017
from ENSDF data base. 2287701100018
Analysis for W-182(n,p)Ta-182 and W-183(n,x)Ta-182 2287701100019
reactions cross sections is based on 1221.4 keV 2287701100020
gamma-line, which is less intensive than 1121.3 keV to2287701100021
avoid interference with natural background for the 2287701100022
former one. 2287701100023
Contribution from W-183(n,np)Ta-182 reaction to Ta-1822287701100024
production can not be neglected even around 14 MeV. 2287701100025
STATUS Fig. 4 top left of C,2007NICE,1,559,200704. 2287701100026
Fig. 1 middle bottom left of C,2008VILLIG,75,200810.2287701100027
ENDBIB 25 0 2287701100028
NOCOMMON 0 0 2287701100029
NODATA 0 0 2287701100030
ENDSUBENT 29 0 2287701199999
SUBENT 22877012 20090914 20100416 2287701200001
BIB 5 19 2287701200002
REACTION (74-W-183(N,P)73-TA-183,,SIG) 2287701200003
SAMPLE Natural tungsten samples were prepared by either 2287701200004
punching discs of 13mm diameter or by cutting squares 2287701200005
of 1 cm**2 from metallic foil.Depending on energy of 2287701200006
measured gamma-rays,samples of 0.1 or 0.25mm thickness2287701200007
were used to minimize gamma-ray attenuation. 2287701200008
Isotopic composition: W-180 - (0.12+-0.01)%, 2287701200009
W-182 - (26.50+-0.16)%, W-183 - (14.34+-0.04)%, 2287701200010
W-184 - (30.64+-0.02)%, W-186 - (28.43+-0.19)%. 2287701200011
The enriched W-183 sample was prepared from metal 2287701200012
powder canned in plexiglass container. Isotopic 2287701200013
composition: W-182 -(2.11+-2)%,W-183 -(96.30+-0.03)%, 2287701200014
W-184 - (1.58+-0.02)%, W-186 - (0.005+-0.002)%. 2287701200015
DECAY-DATA (73-TA-183,5.1D,DG,246.0587,0.27) 2287701200016
ANALYSIS Decay parameters applied in data analysis were taken 2287701200017
from ENSDF data base. 2287701200018
Contribution from W-184(n,np)Ta-183 reaction to Ta-1832287701200019
production can not be neglected even around 14 MeV. 2287701200020
STATUS Fig. 4 bottom left of C,2007NICE,1,559,200704.2287701200021
ENDBIB 19 0 2287701200022
NOCOMMON 0 0 2287701200023
NODATA 0 0 2287701200024
ENDSUBENT 23 0 2287701299999
SUBENT 22877013 20090914 20100416 2287701300001
BIB 5 18 2287701300002
REACTION (74-W-184(N,P)73-TA-184,,SIG) 2287701300003
SAMPLE Natural tungsten samples were prepared by either 2287701300004
punching discs of 13mm diameter or by cutting squares 2287701300005
of 1 cm**2 from metallic foil.Depending on energy of 2287701300006
measured gamma-rays,samples of 0.1 or 0.25mm thickness2287701300007
were used to minimize gamma-ray attenuation. 2287701300008
Isotopic composition: W-180 - (0.12+-0.01)%, 2287701300009
W-182 - (26.50+-0.16)%, W-183 - (14.34+-0.04)%, 2287701300010
W-184 - (30.64+-0.02)%, W-186 - (28.43+-0.19)%. 2287701300011
The enriched W-184 sample was prepared from metal 2287701300012
powder canned in plexiglass container. Isotopic 2287701300013
composition: W-180 <0.003%, W-182 - 0.82%, 2287701300014
W-183 - 1.34%, W-184 - 95.2%, W-186 - 2.64%. 2287701300015
DECAY-DATA (73-TA-184,8.7HR,DG,414.01,0.72) 2287701300016
ANALYSIS Decay parameters applied in data analysis were taken 2287701300017
from ENSDF data base. 2287701300018
STATUS Fig. 4 top right of C,2007NICE,1,559,200704 . 2287701300019
Fig.2 bottom left of R,EUR-22794,117,2007. 2287701300020
ENDBIB 18 0 2287701300021
NOCOMMON 0 0 2287701300022
NODATA 0 0 2287701300023
ENDSUBENT 22 0 2287701399999
SUBENT 22877014 20090914 20100416 2287701400001
BIB 5 19 2287701400002
REACTION (74-W-186(N,P)73-TA-186,,SIG) 2287701400003
SAMPLE Natural tungsten samples were prepared by either 2287701400004
punching discs of 13mm diameter or by cutting squares 2287701400005
of 1 cm**2 from metallic foil.Depending on energy of 2287701400006
measured gamma-rays,samples of 0.1 or 0.25mm thickness2287701400007
were used to minimize gamma-ray attenuation. 2287701400008
Isotopic composition: W-180 - (0.12+-0.01)%, 2287701400009
W-182 - (26.50+-0.16)%, W-183 - (14.34+-0.04)%, 2287701400010
W-184 - (30.64+-0.02)%, W-186 - (28.43+-0.19)%. 2287701400011
The enriched W-186 sample was prepared from metal 2287701400012
powder canned in plexiglass container. Isotopic 2287701400013
composition: W-180 <0.005%, W-182 - 0.65%, 2287701400014
W-183 - 0.45%, W-184 - 2.2 %, W-186 - 96.7%. 2287701400015
DECAY-DATA (73-TA-186,10.5MIN,DG,122.3,0.25, 2287701400016
DG,737.5,0.29) 2287701400017
ANALYSIS Decay parameters applied in data analysis were taken 2287701400018
from ENSDF data base. 2287701400019
STATUS (PRELM) Fig. 4 bottom right of C,2007NICE,1,559,200704.2287701400020
Preliminary data. 2287701400021
ENDBIB 19 0 2287701400022
NOCOMMON 0 0 2287701400023
NODATA 0 0 2287701400024
ENDSUBENT 23 0 2287701499999
SUBENT 22877015 20090914 20100416 2287701500001
BIB 5 26 2287701500002
REACTION (74-W-183(N,X)73-TA-182,,SIG) 2287701500003
SAMPLE Natural tungsten samples were prepared by either 2287701500004
punching discs of 13mm diameter or by cutting squares 2287701500005
of 1 cm**2 from metallic foil.Depending on energy of 2287701500006
measured gamma-rays,samples of 0.1 or 0.25mm thickness2287701500007
were used to minimize gamma-ray attenuation. 2287701500008
Isotopic composition: W-180 - (0.12+-0.01)%, 2287701500009
W-182 - (26.50+-0.16)%, W-183 - (14.34+-0.04)%, 2287701500010
W-184 - (30.64+-0.02)%, W-186 - (28.43+-0.19)%. 2287701500011
The enriched W-183 sample was prepared from metal 2287701500012
powder canned in plexiglass container. Isotopic 2287701500013
composition: W-182 -(2.11+-2)%,W-183 -(96.30+-0.03)%, 2287701500014
W-184 - (1.58+-0.02)%, W-186 - (0.005+-0.002)%. 2287701500015
DECAY-DATA (73-TA-182,114.43D,DG,1221.4,0.270) 2287701500016
ANALYSIS Decay parameters applied in data analysis were taken 2287701500017
from ENSDF data base. 2287701500018
Analysis for W-183(n,x)Ta-182 reaction cross section 2287701500019
is based on 1221.4 keV gamma-line, which is less 2287701500020
intensive than 1121.3 keV to avoid interference with 2287701500021
natural background for the former one. 2287701500022
Contribution from W-184(n,np)Ta-183 reaction to Ta-1832287701500023
production can not be neglected even around 14 MeV. 2287701500024
STATUS Fig. 5 top left of C,2007NICE,1,559,200704. 2287701500025
Fig. 1 bottom middle left of C,2008VILLIG,75,200810,2287701500026
(there is a mistake in Fig.1 -data of W-183(n,x)Ta-1822287701500027
were presented twice), newer data. 2287701500028
ENDBIB 26 0 2287701500029
NOCOMMON 0 0 2287701500030
NODATA 0 0 2287701500031
ENDSUBENT 30 0 2287701599999
SUBENT 22877016 20090914 20100416 2287701600001
BIB 5 17 2287701600002
REACTION (74-W-184(N,X)73-TA-183,,SIG) 2287701600003
SAMPLE Natural tungsten samples were prepared by either 2287701600004
punching discs of 13mm diameter or by cutting squares 2287701600005
of 1 cm**2 from metallic foil.Depending on energy of 2287701600006
measured gamma-rays,samples of 0.1 or 0.25mm thickness2287701600007
were used to minimize gamma-ray attenuation. 2287701600008
Isotopic composition: W-180 - (0.12+-0.01)%, 2287701600009
W-182 - (26.50+-0.16)%, W-183 - (14.34+-0.04)%, 2287701600010
W-184 - (30.64+-0.02)%, W-186 - (28.43+-0.19)%. 2287701600011
The enriched W-184 sample was prepared from metal 2287701600012
powder canned in plexiglass container. Isotopic 2287701600013
composition: W-180 <0.003%, W-182 - 0.82%, 2287701600014
W-183 - 1.34%, W-184 - 95.2%, W-186 - 2.64%. 2287701600015
DECAY-DATA (73-TA-182,114.43D,DG,1221.4,0.270) 2287701600016
ANALYSIS Decay parameters applied in data analysis were taken 2287701600017
from ENSDF data base. 2287701600018
STATUS Fig. 5 bottom left of C,2007NICE,1,559,200704.2287701600019
ENDBIB 17 0 2287701600020
NOCOMMON 0 0 2287701600021
NODATA 0 0 2287701600022
ENDSUBENT 21 0 2287701699999
SUBENT 22877017 20081015 20090121 2287701700001
BIB 5 17 2287701700002
REACTION (74-W-186(N,X)73-TA-185,,SIG) 2287701700003
SAMPLE Natural tungsten samples were prepared by either 2287701700004
punching discs of 13mm diameter or by cutting squares 2287701700005
of 1 cm**2 from metallic foil.Depending on energy of 2287701700006
measured gamma-rays,samples of 0.1 or 0.25mm thickness2287701700007
were used to minimize gamma-ray attenuation. 2287701700008
Isotopic composition: W-180 - (0.12+-0.01)%, 2287701700009
W-182 - (26.50+-0.16)%, W-183 - (14.34+-0.04)%, 2287701700010
W-184 - (30.64+-0.02)%, W-186 - (28.43+-0.19)%. 2287701700011
The enriched W-186 sample was prepared from metal 2287701700012
powder canned in plexiglass container. Isotopic 2287701700013
composition: W-180 <0.005%, W-182 - 0.65%, 2287701700014
W-183 - 0.45%, W-184 - 2.2 %, W-186 - 96.7%. 2287701700015
DECAY-DATA (73-TA-182,114.43D,DG,1221.4,0.270) 2287701700016
ANALYSIS Decay parameters applied in data analysis were taken 2287701700017
from ENSDF data base. 2287701700018
STATUS Fig. 5 top right of 1st reference. 2287701700019
ENDBIB 17 0 2287701700020
NOCOMMON 0 0 2287701700021
NODATA 0 0 2287701700022
ENDSUBENT 21 0 2287701799999
SUBENT 22877018 20090914 20100416 2287701800001
BIB 5 12 2287701800002
REACTION (74-W-186(N,2N)74-W-185-M,,SIG) 2287701800003
SAMPLE An enriched in W-186 sample was used for measurements 2287701800004
due to interference from W-184(n,g)W-185m induced from 2287701800005
low-energy neutrons. 2287701800006
The enriched W-186 sample was prepared from metal 2287701800007
powder canned in plexiglass container. Isotopic 2287701800008
composition: W-180 <0.005%, W-182 - 0.65%, 2287701800009
W-183 - 0.45%, W-184 - 2.2 %, W-186 - 96.7%. 2287701800010
DECAY-DATA (73-TA-182,114.43D,DG,1221.4,0.270) 2287701800011
ANALYSIS Decay parameters applied in data analysis were taken 2287701800012
from ENSDF data base. 2287701800013
STATUS Fig. 5 bottom right of C,2007NICE,1,559,200704.2287701800014
ENDBIB 12 0 2287701800015
NOCOMMON 0 0 2287701800016
NODATA 0 0 2287701800017
ENDSUBENT 16 0 2287701899999
SUBENT 22877019 20090914 20100416 2287701900001
BIB 5 18 2287701900002
REACTION (74-W-184(N,A)72-HF-181,,SIG) 2287701900003
SAMPLE Natural tungsten samples were prepared by either 2287701900004
punching discs of 13mm diameter or by cutting squares 2287701900005
of 1 cm**2 from metallic foil.Depending on energy of 2287701900006
measured gamma-rays,samples of 0.1 or 0.25mm thickness2287701900007
were used to minimize gamma-ray attenuation. 2287701900008
Isotopic composition: W-180 - (0.12+-0.01)%, 2287701900009
W-182 - (26.50+-0.16)%, W-183 - (14.34+-0.04)%, 2287701900010
W-184 - (30.64+-0.02)%, W-186 - (28.43+-0.19)%. 2287701900011
The enriched W-184 sample was prepared from metal 2287701900012
powder canned in plexiglass container. Isotopic 2287701900013
composition: W-180 <0.003%, W-182 - 0.82%, 2287701900014
W-183 - 1.34%, W-184 - 95.2%, W-186 - 2.64%. 2287701900015
DECAY-DATA (72-HF-181,42.39D,DG,482.10,0.805) 2287701900016
ANALYSIS Decay parameters applied in data analysis were taken 2287701900017
from ENSDF data base. 2287701900018
STATUS Fig. 6 top of 1st reference. 2287701900019
Fig.2 bottom middle, right of 2nd reference. 2287701900020
ENDBIB 18 0 2287701900021
NOCOMMON 0 0 2287701900022
NODATA 0 0 2287701900023
ENDSUBENT 22 0 2287701999999
SUBENT 22877020 20090914 20100416 2287702000001
BIB 5 18 2287702000002
REACTION (74-W-186(N,A)72-HF-183,,SIG) 2287702000003
SAMPLE Natural tungsten samples were prepared by either 2287702000004
punching discs of 13mm diameter or by cutting squares 2287702000005
of 1 cm**2 from metallic foil.Depending on energy of 2287702000006
measured gamma-rays,samples of 0.1 or 0.25mm thickness2287702000007
were used to minimize gamma-ray attenuation. 2287702000008
Isotopic composition: W-180 - (0.12+-0.01)%, 2287702000009
W-182 - (26.50+-0.16)%, W-183 - (14.34+-0.04)%, 2287702000010
W-184 - (30.64+-0.02)%, W-186 - (28.43+-0.19)%. 2287702000011
The enriched W-186 sample was prepared from metal 2287702000012
powder canned in plexiglass container. Isotopic 2287702000013
composition: W-180 <0.005%, W-182 - 0.65%, 2287702000014
W-183 - 0.45%, W-184 - 2.2 %, W-186 - 96.7%. 2287702000015
DECAY-DATA (72-HF-183,1.068HR,DG,783.753,0.66) 2287702000016
ANALYSIS Decay parameters applied in data analysis were taken 2287702000017
from ENSDF data base. 2287702000018
STATUS Fig. 6 bottom of C,2007NICE,1,559,200704 . 2287702000019
Fig.2 bottom right of R,EUR-22794,117,2007. 2287702000020
ENDBIB 18 0 2287702000021
NOCOMMON 0 0 2287702000022
NODATA 0 0 2287702000023
ENDSUBENT 22 0 2287702099999
SUBENT 22877021 20090914 20100416 2287702100001
BIB 7 17 2287702100002
REACTION (40-ZR-90(N,X)39-Y-89-M,,SIG) 2287702100003
SAMPLE Disc-shaped high-purity natural zirconium of 13 mm 2287702100004
diameter, 0.125mm thickness. Nominal weight 115mg. 2287702100005
DECAY-DATA (39-Y-89-M,15.663SEC,DG,908.960,0.9916) 2287702100006
(40-ZR-89,78.41HR,DG,909.15,0.9904) 2287702100007
FACILITY For Zr-90(n,x) reaction a pneumatic transport system 2287702100008
was used due to short half-life of Y-89m. 2287702100009
ANALYSIS Decay parameters applied in data analysis were taken 2287702100010
from ENSDF data base. 2287702100011
Zr-89g from Zr-90(n,2n)Zr89 reaction decays by EC to 2287702100012
Y-89m can not be neglected.Contribution of Zr-89g to 2287702100013
total 909 keV gamma-activity was estimated to be from 2287702100014
10 to 15% for about 15 cycles of irradiations and 2287702100015
spectrum measurements. 2287702100016
STATUS Fig. 1 bottom left of R,EUR-22794,117,2007. 2287702100017
(SPSDD,22822016) 2287702100018
HISTORY (20090930A) M.M. Subent superseded by 22822016. 2287702100019
ENDBIB 17 0 2287702100020
NOCOMMON 0 0 2287702100021
NODATA 0 0 2287702100022
ENDSUBENT 21 0 2287702199999
ENDENTRY 20 0 2287799999999