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Overview of materials research for fusion reactors

T Muroga, M Gasparotto, S.J Zinkle2002年Fusion Engineering and DesignIF 1.7出版社

AbstractMaterials research for fusion reactors is overviewed from Japanese, EU and US perspectives. Emphasis is placed on programs and strategies for developing blanket structural materials, and recent highlights in research and development for reduced activation ferritic martensitic steels, vanadium alloys and SiC/SiC composites, and in mechanistic experimental and modeling studies. The common critical issue for the candidate materials is the effect of irradiation with helium production. For the qualification of materials up to the full lifetime of a DEMO and Power Plant reactors, an intense neutron source with relevant fusion neutron spectra is crucial. Elaborate use of the presently available irradiation devices will facilitate efficient and sound materials development within the required time scale.

日本語訳

核融合炉のための材料研究を、日本、EU、米国の視点から概観する。ブランケット構造材料の開発のためのプログラムと戦略に重点を置き、低放射化フェライト/マルテンサイト鋼、バナジウム合金、SiC/SiC複合材料の研究開発における最近のハイライトと、機構論的な実験およびモデリング研究に焦点を当てる。候補材料に共通する重要な課題は、ヘリウム生成を伴う照射の影響である。DEMOおよび発電炉の全寿命にわたる材料の認定には、関連する核融合中性子スペクトルを持つ高強度中性子源が不可欠である。現在利用可能な照射装置を巧みに使用することで、要求される時間スケール内での効率的かつ健全な材料開発が促進される。

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