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MHD, heat transfer and stress analysis for the ITER self-cooled blanket design

X.R. Wang, E.A. Mogahed, I.N. Sviatoslavsky1994年Fusion Engineering and DesignIF 1.7出版社

AbstractMagnetohydrodynamic (MHD) effects of the liquid metal self-cooled blanket proposed for ITER are discussed in this paper. Scoping calculations of heat transfer, MHD pressure drop and structure stresses at a steady state for the self-cooled lithium/vanadium inboard blanket design have been performed in order to show if the blanket option can meet the prescribed design criteria, or if modifications are required. The finite element computer code ANSYSTM (DeSalvo and Gorman, ANSYS User Manual, Swanson Analysis System, Inc., 1989) is used to compute two-dimensional temperature and stress distribution in the inboard blanket. The results of the investigation indicate that the ITER self-cooled lithium/vanadium blanket can satisfy the design criteria from the standpoint of heat transfer, MHD pressure drop and stresses. A comfortable safety margin can be obtained if insulting materials are used to decouple the conductive walls from the eddy currents resulting from the flow of liquid metals across magnetic fields.

日本語訳

本論文では、ITER用に提案された液体金属自己冷却ブランケットの磁気流体力学(MHD)効果について議論する。自己冷却リチウム/バナジウム内側ブランケット設計について、定常状態における熱伝達、MHD圧力損失、および構造応力のスコーピング計算を実施し、このブランケットオプションが設計基準を満たすことができるかどうか、または修正が必要かどうかを示す。有限要素コードANSYS™(DeSalvo and Gorman、ANSYSユーザーマニュアル、Swanson Analysis Systems, Inc.、1989年)を用いて、内側ブランケットの二次元温度分布と応力分布を計算する。調査結果は、ITER自己冷却リチウム/バナジウムブランケットが、熱伝達、MHD圧力損失、および応力の観点から設計基準を満たすことができることを示している。絶縁材料を使用して導電性壁と磁場横断液体金属流れに起因する渦電流をデカップリングすれば、十分な安全余裕を得ることができる。

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