FusionPapers
図版検索トレンドwiki日本の研究
© 2026 FUSIONPAPERS
About法務情報
トップに戻る

Concepts and prototype elements of the low-Z wall protection for the stellarator W7-X

H Greuner, J Glagla, O Jandl, B Mendelevitch, R Rieck2001年Fusion Engineering and DesignIF 1.7出版社

AbstractStationary operation, envisaged at WENDELSTEIN 7-X, demands for an active cooled wall protection system. To minimise the radiation losses of the plasma during long pulse operation the inner surface of the vacuum vessel has to be covered completely with materials having low atomic numbers. Unlike from the target plates (receiving a high heat flux of up to 10 MW/m2) that consist of Carbon Fibre Composite (CFC) brazed on a cooling structure, a more simple solution for the Plasma Facing Components (PFC) on the basis of CFC tiles clamped on a cooling structure or larger stainless steel (SS) -panels covered with B4C will be developed for the less loaded baffle areas of the divertor and the 120 m2 wall protection. The choice of the components to be installed in the various areas for wall protection will be determined mainly by the conditions of the physics of the plasma, additional loads by plasma heating (mainly neutral beam injection, NBI and electron cyclotron resonance heating, ECRH), demands by the diagnostics and the geometrical restrictions at different locations in the vacuum vessel.

日本語訳

定常運転が想定されているWENDELSTEIN 7-Xでは、能動的な壁保護システムの要求が生じる。長時間パルス運転中のプラズマによる放射損失を最小化するため、真空容器の内表面は低原子番号材料で完全に覆われなければならない。最大10 MW/m²の高い熱流束を受けるターゲット板とは異なり、ターゲット板は冷却構造にろう付けされた炭素繊維複合材(CFC)で構成されるが、ダイバータのバッフル領域および120 m²の壁保護部では、負荷がより小さいため、冷却構造にクランプされたCFCタイル、またはB₄Cで被覆された大型ステンレス鋼(SS)パネルに基づく、より簡素なプラズマ対向機器(PFC)の解決策が開発されるであろう。壁保護のさまざまな領域に設置される構成要素の選定は、主にプラズマ物理の条件、プラズマ加熱による追加負荷(主に中性粒子ビーム入射(NBI)および電子サイクロトロン共鳴加熱(ECRH))、診断装置の要求、ならびに真空容器内の異なる位置における幾何学的制約によって決定されるであろう。

装置

wendelstein-7x高精度(タイトル一致)

wiki

StellaratorW7-X
この論文にはまだAI要約がありません。

関連論文

The plasma system of RFX

1994Fusion Engineering and Design

Thermal reradiation in the NET/ITER plasma chamber

1991Fusion Engineering and Design

Overview of the first Wendelstein 7-X long pulse campaign with fully water-cooled plasma facing components

2024Nuclear Fusion

Electron transport barrier and high confinement in configurations with internal islands close to the plasma edge of W7-X

2024Nuclear Fusion

Progress in the design of in-vessel components for ITER

1995Fusion Engineering and Design

Electron cyclotron resonance heating in the Wendelstein VII-A stellarator

1986Plasma Physics and Controlled Fusion

Status of WENDELSTEIN 7-X construction

2003Nuclear Fusion

Optimisation of target plates for the W7-X divertor at stationary operation

2001Fusion Engineering and Design

Electron-cyclotron-resonance heating in Wendelstein 7-X: A versatile heating and current-drive method and a tool for in-depth physics studies

2019Plasma Physics and Controlled Fusion

Major results from the first plasma campaign of the Wendelstein 7-X stellarator

2017Nuclear Fusion