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Damage Calculation for First Wall Submitted to High Neutron Flux in a Tokamak

Published online by Cambridge University Press:  13 February 2015

C.E. Velasquez
Affiliation:
Departamento de Engenharia Nuclear – Escola de Engenharia Universidade Federal de Minas Gerais Avenida Antônio Carlos, 6627, Pampulha 31270-901 – Belo Horizonte, Tel/Fax: 55-31-34096662, MG, Brasil
M. A. F. Veloso
Affiliation:
Departamento de Engenharia Nuclear – Escola de Engenharia Universidade Federal de Minas Gerais Avenida Antônio Carlos, 6627, Pampulha 31270-901 – Belo Horizonte, Tel/Fax: 55-31-34096662, MG, Brasil Instituto Nacional de Ciências e Tecnologia de Reatores Nucleares Inovadores/CNPq, [email protected]
A. L. Costa
Affiliation:
Departamento de Engenharia Nuclear – Escola de Engenharia Universidade Federal de Minas Gerais Avenida Antônio Carlos, 6627, Pampulha 31270-901 – Belo Horizonte, Tel/Fax: 55-31-34096662, MG, Brasil Instituto Nacional de Ciências e Tecnologia de Reatores Nucleares Inovadores/CNPq, [email protected]
C. Pereira
Affiliation:
Departamento de Engenharia Nuclear – Escola de Engenharia Universidade Federal de Minas Gerais Avenida Antônio Carlos, 6627, Pampulha 31270-901 – Belo Horizonte, Tel/Fax: 55-31-34096662, MG, Brasil Instituto Nacional de Ciências e Tecnologia de Reatores Nucleares Inovadores/CNPq, [email protected]
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Abstract

The displacement per atom (dpa) has been a specific issue to evaluate the damage in the first wall of the Tokamak. Two different first wall materials were evaluated. In this study, MCNP5 code was used to obtain the neutron flux, the energy deposition and the main reaction rates, on the inboard and outboard first wall. The damage calculations were performed by the SPECTER code using the neutronic parameters obtained by MCNP5. The Tokamak reactor modeled has similar dimensions to the ITER. Tungsten and beryllium alloys were simulated on the outboard first wall. The results indicate which material has a higher resistance to be damage and dpa values for the analyzed material.

Type
Articles
Copyright
Copyright © Materials Research Society 2015 

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References

REFERENCES

Lee, Bo-Young, Oh, Joo-Hee and Ko, Seung-Kook, Lee, Hee-Seock,”Calculation of the Damage and the H and He Productions for 14.1-MeV Neutrons”, Journal of the Korean Physical Society, Vol. 63, No.1, July 2013, pp.3640 CrossRefGoogle Scholar
Van Hoey, Olivier, “Visible light measurements on the COMPASS tokamak”, Faculty of Engineering Department of Applied Physics, May 20, 2010 Google Scholar
Naujoks, Dirk, “Plasma Material Interaction in Controlled Fusion”, Springer; 2006 editionGoogle Scholar
Stewart, Saralyn, “Tokamak Experiments Come Clean about Impurity Transport”, APS Physics, 2011 Google Scholar
X-5 Monte Carlo Team, MCNP – A General Monte Carlo N-Particle Transport Code, Version 5, Volume II: User’s Guide University of California, Los Alamos National Laboratory. (2003)Google Scholar
Greenwood, L. R., Smither, R. K., “SPECTER: Neutron Damage Calculations for Materials Irradiation”, Argonne National Laboratory, Illinois,January 1985.CrossRefGoogle Scholar
Velasquez, C.E., Barros, G. P., Pereira, C. ; Veloso, M.A.F. ; Costa, A.L.Axial Neutron Flux Evaluation in a Tokamak System: a Possible Transmutation Blanket Position for a Fusion-Fission Transmutation System”, Brazilian Journal of Physics, Vol.42/3-4, pp. 237247, (2012).CrossRefGoogle Scholar
Velasquez, C.E. ; Pereira, C. ; Veloso, M.A.F. ; Costa, A.L.Modelling effects on axial neutron flux in a Tokamak device”, Progress in Nuclear Energy (New Series), Vol.2014, pp. 18, (2014).Google Scholar
ITER-Final Design Report: http://www.naka.jaea.go.jp/ITER/FDR/, (2001).Google Scholar
Wu, Y. et al., “CAD-based interface programs for fusion neutron transport simulation”, Fusion Engineering and Design, Vol. 84, 19871992, (2009).CrossRefGoogle Scholar
Robinson, A., El Guebaly, L., Henderson, D., W-Based Alloys for Advanced Divertor Designs: Detailed Activation and Radiation Damage Analysis, Fusion Technology Insitute, University of Wisconsin, October (2010)Google Scholar
Michael Andrew Clemens, “Energy Deposition Mechanisms for Proton- and Neutron-Induced Single Event Upsets in Modern Electronic Devices”, Graduate School of Vanderbilt University, Nashville-Tennessee, May 2012 Google Scholar