EFF-DOC-893, EFF/EAF Moni toring Meeting, NEA-DB, P aris, May 10-12, 2004 1 Sensitivity of Activation Cross Sections of Tungsten to Nuclear Reaction Mechanisms V. Avrigeanu 1 , R. Eichin 2 , R.A. Forrest 3 , H. Freiesleben 2 , M. Herman 4 , A.J. Koning 5 , and K. Seidel 2 EFF-DOC-893 1 EURATOM-MEC Fusion Association, “Horia Hulubei” National Institute for Physics & Nuclear Engineering, P.O Box MG-6, 76900 Bucharest, Romania 2 EURATOM-FZK/TUD Fusion Association, Technische Universität Dresden, D-01062 Dresden, Germany 3 EURATOM-UKAEA Fusion Association, Culham Science Center, Abingdon OX143DB, United Kingdom 4 Brookhaven National Laboratory, P.O. Box 5000, Upton, NY 11973-5000 5 Nuclear Research and Consultancy Group NRG, P.O. Box 25, 1755 ZG Petten, The Netherlands
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Sensitivity of Activation Cross Sections of Tungsten to Nuclear Reaction Mechanisms
EFF-DOC-893. Sensitivity of Activation Cross Sections of Tungsten to Nuclear Reaction Mechanisms. 1 EURATOM-MEC Fusion Association, “Horia Hulubei” National Institute for Physics & Nuclear Engineering, P.O Box MG-6, 76900 Bucharest, Romania - PowerPoint PPT Presentation
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EFF-DOC-893, EFF/EAF Monitoring Meeting, NEA-DB, Paris, May 10-12, 2004
1
Sensitivity of Activation Cross Sections of Tungsten to Nuclear Reaction Mechanisms
V. Avrigeanu1, R. Eichin2, R.A. Forrest3, H. Freiesleben2, M. Herman4, A.J. Koning5, and K. Seidel2
EFF-DOC-893
1EURATOM-MEC Fusion Association, “Horia Hulubei” National Institute for Physics & Nuclear Engineering, P.O Box MG-6, 76900 Bucharest, Romania2EURATOM-FZK/TUD Fusion Association, Technische Universität Dresden, D-01062 Dresden, Germany3EURATOM-UKAEA Fusion Association, Culham Science Center, Abingdon OX143DB, United Kingdom4Brookhaven National Laboratory, P.O. Box 5000, Upton, NY 11973-50005Nuclear Research and Consultancy Group NRG, P.O. Box 25, 1755 ZG Petten, The Netherlands
EFF-DOC-893, EFF/EAF Monitoring Meeting, NEA-DB, Paris, May 10-12, 2004
2
Outline [e.g.1, EFF-DOC-872, Nov. 2003]
• Nuclear cross sections calculations- Search for appropriate optical model potentials: n+182,183,184,186W
- p+ 181Ta- Compilation of the available experimental data (E<20 MeV)- Nuclear model calculations (E<20 MeV)- Comparison with all activation experimental data
• Processing of model calculations results- Cross sections of all individual channels with activation data-
• • [Benchmark experiment analysis updating
– calculated-to-experimental (C/E) activity: reduced deviation from unity ]
1P. Pereslavtsev and U. Fischer, Evaluation of n+184W cross-section data for EFF up to 150 MeV
EFF-DOC-893, EFF/EAF Monitoring Meeting, NEA-DB, Paris, May 10-12, 2004
non=2.36±0.05 b at incident energy E=14.1 MeVcorresponding to inelastic scattering from above ~2 MeV of the excitation energy18, and a crosssection of ~0.04 b for statistical inelastic scattering on low-lying levels below ~2 MeV.
b =(N-Z)/A
EFF-DOC-893, EFF/EAF Monitoring Meeting, NEA-DB, Paris, May 10-12, 2004
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Comparison of experimental and calculated neutron scattering parameters of 182,184,186W
EFF-DOC-893, EFF/EAF Monitoring Meeting, NEA-DB, Paris, May 10-12, 2004
15
Comparison of the measured and calculated reaction cross sections for the target nucleus 180W
Calculated values by means of the computer codes EMPIRE-II and TALYS with default global parameters (except the local OMPs) and STAPRE-H with local parameter set given in this work.
0.01 0.1 1
0.1
1
Bokhovko+ (1986)
CC+GDH+HF EMPIRE-II TALYS-0.58
(a)
180W(n,)181
W
(b)
10 15 200.00
0.01
0.02
CC+GDH+HF TALYS-0.58
[1+ 8.152 h]
Qaim+ (1975)
(b)
180W(n,p)
180mTa
10 15 200
1
2
Qaim+ (1975)
CC+GDH+HF EMPIRE-II TALYS-0.58
(c)
180W(n,2n)
179g+mW
(b
)
En (MeV)10 15 200.0
0.4
0.8
CC+GDH+HF TALYS-0.58
[1/2- 6.4 min]
Qaim+ (1975)Filatenkov+ (2002)
(d)
180W(n,2n)
179mW
En (MeV)
EFF-DOC-893, EFF/EAF Monitoring Meeting, NEA-DB, Paris, May 10-12, 2004
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Comparison of the measured and calculated reaction cross sections for the target nucleus 182W
Calculations with EMPIRE-II and TALYS, and default global parameters (except local OMPs), and STAPRE-H with local parameter set. Normalization factor of 1.078 [Vonach+, 1990] is applied to data of Frehaut+
EFF-DOC-893, EFF/EAF Monitoring Meeting, NEA-DB, Paris, May 10-12, 2004
17
Comparison of the measured and calculated reaction cross sections for the target nucleus 183W
Calculated values by means of the computer codes EMPIRE-II and TALYS with default global parameters (except the local OMPs) and STAPRE-H with local parameter set given in this work.
EFF-DOC-893, EFF/EAF Monitoring Meeting, NEA-DB, Paris, May 10-12, 2004
18
Comparison of the measured and calculated reaction cross sections for the target nucleus 184W
Calculations with EMPIRE-II and TALYS, and default global parameters (except local OMPs), and STAPRE-H with local parameter set. Normalization factor of 1.078 [Vonach+, 1990] is applied to data of Frehaut+ (1980).
EFF-DOC-893, EFF/EAF Monitoring Meeting, NEA-DB, Paris, May 10-12, 2004
19
Comparison of the measured and calculated reaction cross sections for the target nucleus 186W
Calculations with EMPIRE-II and TALYS, and default global parameters (except local OMPs), and STAPRE-H with local parameter set. Normalization factor of 1.078 [Vonach+, 1990] is applied to data of Frehaut+ (1980).
EFF-DOC-893, EFF/EAF Monitoring Meeting, NEA-DB, Paris, May 10-12, 2004
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Sensitivity of calculated (n,2n) reaction cross sections vs. reaction mechanisms & model parameters
Calculations with EMPIRE-II and default global parameters excepting local OMPs. A normalization factor of 1.078 (Vonach+, 1990) was applied to data of Frehaut+ (1980).