動力・エネルギー技術の最前線講演論文集 : シンポジウム
Online ISSN : 2424-2950
セッションID: NP3-01
会議情報
核融合発電実証プラント用ダイバータの設計と研究開発の現状(NP3 新型炉技術)
江里 幸一郎鈴木 哲廣瀬 貴規佐藤 和義秋場 真人
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会議録・要旨集 フリー

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JAERI has carried out design and R&Ds activities on divertors for the future DEMO plant, which needs to handle high heat load more than 10MW/m^2. In DEMO designs, F82H, one of Reduced Activation Ferritic Martensitic (RAFM) steels, is applied to cooling structure of Plasma-Facing Components (PFCs) and is covered with tungsten material as armor against ions and neutral particle fluxes. Thermal analyses show that divertor structure of a F82H cooling tube with monoblock tungsten armors meet a design requirement to remove 10MW/m^2 without an excess of temperature in F82H over the upper limit of its service temperature. Thermal and mechanical tests of F82H cooling tube such as Critical Heat Flux and thermal fatigue have been performed to assess the applicability of F82H to high heat flux components. The results of joining tests between tungsten and F82H with brazing and direct diffusion bonding processes are also reported.
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© 2004 一般社団法人 日本機械学会
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