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

The natural divertor design for a compact tokamak transmutation reactor

Y.P Chen, L.J Qiu1998年Fusion Engineering and DesignIF 1.7出版社

AbstractA Compact Tokamak Transmutation Reactor natural divertor design is proposed. B2 code is used for this design and edge plasma main physics parameters in the wider SOL (SOL thickness=15 cm) are obtained. The peak value of energy flux and electron temperature near the natural divertor target plate, Pmax=13.37 MW m−2 and Temax=15.55 eV, respectively, are less than in the case of conventional tokamak thin SOL (generally, SOL thickness=5 cm), Pmax=27.92 MW m−2 and Temax=78.85 eV. When radiation gas (cold He gas, energy E0=0.1 eV, flux φ=1.3×1023 m−2 s−1) is puffed into the divertor room from the bottom of the natural divertor, the Pmax value is reduced to 3.861 MW m−2. He gas puffing is applied to the design. A basic structural design has been completed and the main features or key parameters have been introduced.

日本語訳

コンパクトなトカマク核変換炉の自然ダイバータ設計を提案する。本設計にはB2コードを用い、より広いSOL(SOL厚さ=15 cm)におけるエッジプラズマの主要物理パラメータを得た。自然ダイバータターゲット板近傍でのエネルギー流束のピーク値と電子温度は、それぞれPmax=13.37 MW m−2およびTemax=15.55 eVであり、従来のトカマクの薄いSOL(一般的にSOL厚さ=5 cm)の場合のPmax=27.92 MW m−2およびTemax=78.85 eVよりも低い。自然ダイバータの底部からダイバータ室へ放射ガス(冷たいHeガス、エネルギーE0=0.1 eV、フラックスφ=1.3×1023 m−2 s−1)をパフすると、Pmax値は3.861 MW m−2に低減される。本設計にはHeガスパフを適用する。基本構造設計が完了し、主要な特徴および主要パラメータを紹介した。

wiki

Divertor
この論文にはまだAI要約がありません。

関連論文

Divertor modeling and design for a low-aspect-ratio tokamak transmutation reactor

2000Fusion Engineering and Design

Divertor modelling for the design of the HT-7U tokamak*

2002Nuclear Fusion

Engineering design of the TITAN-II divertor

1989Fusion Engineering and Design

Divertor and edge plasma properties in doublet III expanded boundary discharges

1986Nuclear Fusion

Simulation study for divertor design to handle huge exhaust power in the SlimCS DEMO reactor

2009Nuclear Fusion

Divertor power load studies for attached L-mode single-null plasmas in TCV

2018Nuclear Fusion

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

2021Nuclear Fusion

Power handling in a highly-radiative negative triangularity pilot plant

2024Plasma Physics and Controlled Fusion

An innovative divertor concept, the fish tail divertor, for reducing the surface temperature on the divertor target plate in EAST tokamak experiments

2023Nuclear Fusion

Developing physics basis for the snowflake divertor in the DIII-D tokamak

2018Nuclear Fusion