ITER Divertor Design(<Special Topic Articles>Trends of Divertor Reserch)
Bibliographic Information
- Other Title
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- ITERのダイバータ設計
- ITER ノ ダイバータ セッケイ
- 2.ITERのダイバータ設計(<小特集>最近のダイバータ研究の動向>)
- ITERのダイバータ設計
- 小特集 最近のダイバータ研究の動向
- ショウ トクシュウ サイキン ノ ダイバータ ケンキュウ ノ ドウコウ
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Abstract
This paper reviews the status of ITER divertor design as described in the Interim Design Report. The ITER divertor must exhaust 300 MW alpha heating power and helium ash. It must also withstand huge loads of electromagnetic force and heat flux associated with disruption. The divertor should also be eifrciently replaced with remote maintenance. Recent divertor experiments and modelling suggest that the radiative divertor approach may provide a feasible solution to the power and particle exhaust. Compatibility of radiative divertor with good confinement (H～2) and high purity (Z_<eff>～1.5) is yet to be demonstrated, and the physics of high density limit remains to be a challenge. The present divertor design based on a cassette scheme is feasible with remote maintenance. Mechanical loads predicted presently are very demanding, but recent progress in VDE (Vertical Displacement Event) control in JT-60U may bring out drastic reduction of its frequency and consequence.
Journal
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- プラズマ・核融合学会誌 = Journal of plasma and fusion research / プラズマ・核融合学会編集委員会 編
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プラズマ・核融合学会誌 = Journal of plasma and fusion research / プラズマ・核融合学会編集委員会 編 72 (9), 858-865, 1996-09
プラズマ・核融合学会
