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

Gas exhaust in the Wendelstein 7-X stellarator during the first divertor operation

U. Wenzel, G. Schlisio, P. Drewelow, M. Krychowiak, R. König, T.S. Pedersen, S. Bozhenkov, V. Haak, A.K. Kharwandikar, S. Lazerson2022年被引用 5Nuclear FusionIF 3出版社

The optimized superconducting stellarator Wendelstein 7-X (W7-X) is equipped with an island divertor for energy control and efficient pumping. We investigated the performance of the island divertor in terms of gas exhaust. For this purpose we have installed 18 pressure gauges in the vacuum vessel. This allowed us to determine the exhaust efficiency, the leakage, the collection efficiency and the compression ratio of the island divertor. These quantities depended strongly on the magnetic configuration. The best performance was obtained in the high-iota configuration. The exhaust efficiency was 2.9%, significantly higher than in the standard configuration (0.44%), and the maximum neutral compression was about 80. The high-iota configuration appears particularly promising for long-pulse operation of W7-X.

日本語訳

最適化された超伝導ステラレータであるWendelstein 7-X(W7-X)には、エネルギー制御と効率的な排気のためのアイランダイバータが装備されている。我々は、ガス排気に関するアイランダイバータの性能を調査した。この目的のため、真空容器内に18個の圧力計を設置した。これにより、アイランダイバータの排気効率、漏洩、捕集効率、および圧縮比を決定することができた。これらの量は磁気配位に強く依存した。最も良い性能は高イオタ配位で得られた。排気効率は2.9%であり、標準配位(0.44%)よりも有意に高く、最大中性粒子圧縮比は約80であった。高イオタ配位は、W7-Xの長時間パルス運転にとって特に有望であると思われる。

装置

wendelstein-7x高精度(タイトル一致)

wiki

DivertorStellaratorWendelstein
この論文にはまだAI要約がありません。

関連論文

First results from divertor operation in Wendelstein 7-X

2019Plasma Physics and Controlled Fusion

First divertor physics studies in Wendelstein 7-X

2019Nuclear Fusion

Performance of Wendelstein 7-X stellarator plasmas during the first divertor operation phase

2019Physics of Plasmas

Divertor concept for the W7-X stellarator and mode of operation

2002Plasma Physics and Controlled Fusion

Overview over the neutral gas pressures in Wendelstein 7-X during divertor operation under boronized wall conditions

2023Plasma Physics and Controlled Fusion

Stable heat and particle flux detachment with efficient particle exhaust in the island divertor of Wendelstein 7-X

2021Nuclear Fusion

Overview of the results from divertor experiments with attached and detached plasmas at Wendelstein 7-X and their implications for steady-state operation

2021Nuclear Fusion

Large wetted areas of divertor power loads at Wendelstein 7-X

2020Nuclear Fusion

Corrigendum: Gas exhaust in the Wendelstein 7-X stellarator during the first divertor operation (2022 Nucl. Fusion 62 096016)

2023Nuclear Fusion

Ultrahigh neutral pressures in the sub-divertor of the Large Helical Device

2024Nuclear Fusion