K-2106 核融合動力炉A-SSTR2プラズマ対向機器の熱構造設計(S27-2 次世代エネルギー源に対応した発電技術(2))(S27 次世代エネルギー源に対応した発電技術)

概要

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A conceptual design of nuclear fusion power reactor A-SSTR2 (Advanced Steady State Tokamak Reactor 2) has been examined in the Japan Atomic Energy Research Institute. The first wall of the blanket uses SiC/SiC composite as the material having excellent advantages of the high heat resistance and the low activation. The first wall is subjected to high heat flux and high energy neutrons or particles from the plasma reacting nuclear fusion, therefore it might generate a significant crack. Heat flux beyond 10 MW/m^2 loads on the divertor plate locally. Tungsten material is assumed as a structural material of the first plate. Concept of liquid divertor is proposed. This paper describes the optimum thermal structural design and the structural integrity evaluation of the first wall and the divertor plate using finite element analysis codes.
2001-08-22