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A review of modelling and simulation of hydrogen behaviour in tungsten at different scales

Guang-Hong Lu, Hong-Bo Zhou, Charlotte S. Becquart2014年被引用 174Nuclear FusionIF 3出版社

Tungsten (W) is considered to be one of the most promising plasma-facing materials (PFMs) for next-step fusion energy systems. However, as a PFM, W will be subjected to extremely high fluxes of low-energy hydrogen (H) isotopes, leading to retention of H isotopes and blistering in W, which will degrade the thermal and mechanical properties of W. Modelling and simulation are indispensable to understand the behaviour of H isotopes including dissolution, diffusion, accumulation and bubble formation, which can contribute directly to the design, preparation and application of W as a PFM under a fusion environment. This paper reviews the recent findings regarding the behaviour of H in W obtained via modelling and simulation at different scales.

日本語訳

タングステン(W)は、次世代核融合エネルギーシステム用のプラズマ対向材料(PFM)の最も有望な材料の一つであると考えられている。しかしながら、PFMとして、Wは極めて高フラックスの低エネルギー水素(H)同位体にさらされ、W中でのH同位体の保持やブリスター形成を引き起こし、Wの熱的・機械的特性を劣化させる。モデリングとシミュレーションは、溶解、拡散、蓄積、気泡形成を含むH同位体の挙動を理解するために不可欠であり、核融合環境下でのPFMとしてのWの設計、作製、応用に直接貢献することができる。本稿では、異なるスケールでのモデリングとシミュレーションによって得られたW中のHの挙動に関する最近の知見をレビューする。

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