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

Author:

Velasquez C.E.,Veloso M. A. F.,Costa A. L.,Pereira C.

Abstract

ABSTRACTThe 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.

Publisher

Springer Science and Business Media LLC

Subject

General Engineering

Reference12 articles.

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2. Axial Neutron Flux Evaluation in a Tokamak System: a Possible Transmutation Blanket Position for a Fusion–Fission Transmutation System

3. 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)

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