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

  • C.E. Velasquez (a1), M. A. F. Veloso (a1) (a2), A. L. Costa (a1) (a2) and C. Pereira (a1) (a2)

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.

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1. 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
2. Van Hoey, Olivier, “Visible light measurements on the COMPASS tokamak”, Faculty of Engineering Department of Applied Physics, May 20, 2010
3. Naujoks, Dirk, “Plasma Material Interaction in Controlled Fusion”, Springer; 2006 edition
4. Stewart, Saralyn, “Tokamak Experiments Come Clean about Impurity Transport”, APS Physics, 2011
5. 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)
6. Greenwood, L. R., Smither, R. K., “SPECTER: Neutron Damage Calculations for Materials Irradiation”, Argonne National Laboratory, Illinois,January 1985.
7. 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).
8. 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).
9. ITER-Final Design Report: http://www.naka.jaea.go.jp/ITER/FDR/, (2001).
10. Wu, Y. et al., “CAD-based interface programs for fusion neutron transport simulation”, Fusion Engineering and Design, Vol. 84, 19871992, (2009).
11. 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)
12. 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

Keywords

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

  • C.E. Velasquez (a1), M. A. F. Veloso (a1) (a2), A. L. Costa (a1) (a2) and C. Pereira (a1) (a2)

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