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Critical heat flux analysis and R&D for the design of the ITER divertor

A.R. Raffray, J. Schlosser, M. Akiba, M. Araki, D. Youchison1999年Fusion Engineering and DesignIF 1.7出版社

AbstractThe vertical target and dump target of the ITER divertor have to be designed for high heat fluxes (up to 20 MW/m2 over ≈10 s). Accommodation of such high heat fluxes gives rise to several issues, including the critical heat flux (CHF) margin which is a key requirement influencing the choice of cooling channel geometry and coolant conditions. An R&D programme was evolved to address the overall CHF issue and to help focus the design. It involved participation of the four ITER home teams and has been very successful in substantially expanding the CHF data base for one-sided heating and in providing more accurate experimental measurements of pressure drop (and derived correlations) for these geometries. This paper describes the major R&D results and the design analysis performed in converging on a choice of reference configuration and parameters which resulted in a CHF margin of ≈1.4 or more for all divertor components.

日本語訳

ITERダイバータの垂直ターゲットおよびダンプターゲットは、高い熱流束(最大20 MW/m²、約10秒間)に耐えるよう設計されなければならない。このような高い熱流束への対応は、冷却チャネル形状および冷却材条件の選択に影響を与える主要な要件である限界熱流束(CHF)マージンなど、いくつかの課題を生じさせる。全体的なCHF問題に対処し、設計の焦点を絞り込むために、研究開発プログラムが実施された。このプログラムには4つのITERホームチームが参加し、片面加熱に対するCHFデータベースの大幅な拡充と、これらの形状に対する圧力損失のより正確な実験的測定に成功した。本論文では、主要な研究開発成果と、すべてのダイバータ構成要素に対して約1.4以上のCHFマージンを確保する参照構成およびパラメータの選定に至った設計解析について述べる。

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