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Review of SiC material development for nuclear fusion applications: Cross-cutting research and emerging opportunities

https://repo.qst.go.jp/records/2003327
https://repo.qst.go.jp/records/2003327
2f2c8686-b48a-4a25-8096-a4e32db0a36a
アイテムタイプ 学術雑誌論文 / Journal Article(1)
公開日 2026-05-25
タイトル
タイトル Review of SiC material development for nuclear fusion applications: Cross-cutting research and emerging opportunities
言語 en
言語
言語 eng
資源タイプ
資源タイプ識別子 http://purl.org/coar/resource_type/c_6501
資源タイプ journal article
著者 Takaaki Koyanagi

× Takaaki Koyanagi

Takaaki Koyanagi

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Takashi Nozawa

× Takashi Nozawa

Takashi Nozawa

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Monica Ferraris

× Monica Ferraris

Monica Ferraris

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Tatsuya Hinoki

× Tatsuya Hinoki

Tatsuya Hinoki

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James Wade-Zhu

× James Wade-Zhu

James Wade-Zhu

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Yutai Katoh

× Yutai Katoh

Yutai Katoh

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抄録
内容記述タイプ Abstract
内容記述 The SiC-based materials, particularly SiC-fiber-reinforced SiC matrix (SiC/SiC) composites, show strong potential for structural and functional applications in future fusion power plants because they can operate at high temperatures with a range of coolants and breeders, thereby enabling higher energy conversion efficiency. This paper presents recent advancements in the development of SiC-based materials, focusing on processing techniques and material performance and resistance under fusion-relevant environments. The processing activities have emphasized near-net-shape fabrication and the joining of SiC subcomponents, with processing methods and material compositions informed by previous irradiation experiments on various grades of SiC. Research on irradiation effects has remained focused on degradation mechanisms and the microstructural optimization of SiC/SiC composites irradiated to high neutron damage levels. Analysis of irradiation defects in SiC has advanced via the application of cutting-edge characterization methods, among which Raman spectroscopy is becoming a common tool to assess atomic-scale chemical disorder. Fusion–fission crosscutting irradiation research has explored combined effects in SiC/SiC composites with application-relevant geometries, including bowing of SiC/SiC composite channels under neutron flux gradients, stress evolution in SiC/SiC composite tubes under throughthickness temperature gradients, and irradiation-enhanced corrosion in SiC. Finally, research opportunities for component testing and assessment under fusion-relevant conditions, in support of emerging concepts from the private fusion sector, are discussed.
書誌情報 Journal of Nuclear Materials

巻 630, p. 156746, 発行日 2026-05
出版者
出版者 ELSEVIER
DOI
識別子タイプ DOI
関連識別子 10.1016/j.jnucmat.2026.156746
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