Abstract

This study is focused on tritium retention and permeation through a 316L stainless steel diagnostic first wall during plasma operations in ITER. A set of data for migration properties is proposed by adjusting the values to fit a simulation using experimental results. A reactive–diffusion model coupled with a mechanical field, solved on 3DS Abaqus finite-element software, is applied to estimate tritium migration. Two-dimensional simulations are compared with one-dimensional simulations and the role of thermal expansion on plastic deformation and trap creation is discussed.

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