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: NP3-02
会議情報
核融合炉・ブランケットの現状と課題 : 耐熱と燃料増殖の両立性(NP3 新型炉技術)
秦野 歳久谷川 尚廣瀬 貴規阿部 哲也榎枝 幹男秋陽 真人
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会議録・要旨集 フリー

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This paper reviews current status of structure designs, development of fabrication technologies and research of basic design data of breeding blanket of fusion power demonstration plant which applies reduced activation ferritic steel as the structural material and high temperature and pressure water as the coolant. In the fusion power demonstration plant, it is required to show the feasibility of self-sufficiency of fuel tritium and power generation with high thermal efficiency. To achieve this requirement, integrity of the blanket structure in high temperature. Supporting R&Ds have been performed and showed significant progress on the fabrication technology development of blanket box structure and breeder and multiplier packed bed structure in the blanket box. This paper introduces the recent topics of the essential R&Ds, corrosion rate measurement of the structural material by high temperature steam and exploration of thermo-mechanical compound data of breeder pebble bed, the effective thermal conductivity of breeder pebble bed influenced by mechanical behavior.
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© 2004 一般社団法人 日本機械学会
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