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论文类型：期刊论文

发表时间：2020-10-01

发表刊物：JOURNAL OF NUCLEAR MATERIALS

收录刊物：SCIE

卷号：539

ISSN号：0022-3115

关键字：Ion irradiations; W fuzz; D retention; Plasma-facing material

摘要：The retention of hydrogen isotopes in W is one of the main limiting factors affecting the design and development of next-step fusion reactors, such as the international thermonuclear experimental reactor (ITER). Here, we report on D retention behavior under the steady-state He/D ion irradiations of polycrystalline W. We find that the D retention behavior in the W bulk is completely suppressed by the growth of high surface-to-volume W fuzz layer (1.1-4.0 mm thick) over the surface. Our analyses show that due to their frequent collisions in the W fuzz layer, the dose of D ions greatly decreases when they collide into the W bulk beneath the fuzz layer. The W fuzz layer with a high surface-to-volume ratio becomes an effective shield against the ion driven diffusion processes. (C) 2020 Elsevier B.V. All rights reserved.