Abstract

Nowadays, three classes of materials are considered the most relevant as the structural materials for fusion facilities: the austenitic steels, reduced activation ferritic-martensitic steels (RAFMS) and V-Cr-Ti alloys. In Russian Federation, the materials of all three types are developed and industrially produced: the ChS-68 austenitic steel, the Ek-181 RAFMS, and the V-4Cr-4Ti alloy. In this work, the deuterium permeability was studied of the fusion-relevant structural materials produced in Russia. Gas-driven permeation measurements were performed in a pressure range of 0.1÷5⋅104 Pa and in a temperature range of 290÷600 °C. Deuterium diffusion and permeation coefficients for the ChS-68 steel were found out. Permeability of the V-4Cr-4Ti alloy was estimated. At the same membrane temperature and D2 pressure at the inlet surface, the deuterium flux permeating through the oxidized Ek-181 RAFMS is the lowest, the flux through the ChS-68 austenitic steel is several times higher, and the flux through vanadium alloy is 3–4.5 orders of magnitude higher.

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