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Thermal-hydraulic design of direct superheated steam blanket for the compact reversed shear tokamak reactor (CREST)

Y Nomoto, T Ishida, H Ise, S Mori, K Okano2001年Fusion Engineering and DesignIF 1.7出版社

AbstractThe compact reversed shear tokamak, CREST, is a cost competitive power reactor concept based on the reversed shear high beta plasma. As the cooling system of CREST blanket, the direct superheated steam cycle is adopted to simplify the heat transport/power generation system and to achieve high thermal efficiency with a water cooled concept. Thermal-hydraulic design of the blanket was performed for the nominal operation, the start-up operation and the partial load operation. As a result of the study, it was confirmed that the direct steam cycle blanket is promising for a power reactor and is feasible not only at the nominal operation condition but also at the reactor start-up and the partial load conditions.

日本語訳

コンパクト逆シアトカマクであるCRESTは、逆シア高ベータプラズマに基づくコスト競争力のある発電炉コンセプトである。CRESTブランケットの冷却システムとして、直接過熱蒸気サイクルを採用し、熱輸送・発電システムの簡素化と、水冷却コンセプトによる高い熱効率の達成を図った。ブランケットの熱流動設計は、定格運転、起動運転、および部分負荷運転に対して実施された。検討の結果、直接蒸気サイクルブランケットは発電炉として有望であり、定格運転条件だけでなく、炉起動時および部分負荷条件においても実現可能であることが確認された。

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Reversed magnetic shearThermal-hydraulics
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