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)

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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.
社団法人日本機械学会の論文
2004-06-22