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

Compact reversed shear tokamak reactor with a superheated steam cycle

K. Okano, Y. Asaoka, T. Yoshida, M. Furuya, K. Tomabechi, Y. Ogawa, N. Sekimura, R. Hiwatari, T. Yamamoto, T. Ishikawa2000年被引用 54Nuclear FusionIF 3出版社

The compact reversed shear tokamak CREST is a costcompetitive reactor concept based on a reversed shear high βplasma and water cooled ferritic steel components. The moderate aspectratio A = 3.4 and the elongation κ = 2.0 of CREST are verysimilar to the case of the ITER advanced mode plasma. Presentation of such aconcept based on the ITER project should be worth while forformulating a fusion development strategy. The achievement of acompetitive cost of electricity (COE) is the first priority forelectric power industries. High β and high thermal efficiency arethe most effective parameters for achieving a competitive COE. In orderto achieve a high efficiency power plant, a superheated steam cycle has been adopted which permits a high thermal efficiency(η = 41%). Current profile control and high speed plasmarotation by neutral beam current drive stabilize the ideal MHDactivity up to the Troyon coefficient βN = 5.5. A costassessment has shown that CREST could generate about 1.16 GW(e)electric power at a competitive cost.

日本語訳

コンパクト逆シアトカマクCRESTは、逆シア高βプラズマと水冷フェライト鋼構成要素に基づくコスト競争力のある炉概念である。CRESTの中程度のアスペクト比A = 3.4と伸長度κ = 2.0は、ITER先進モードプラズマの場合と非常に類似している。このようなITER計画に基づく概念の提示は、核融合開発戦略を策定する上で価値があるはずである。競争力のある発電コスト(COE)の達成は、電力業界にとって最優先事項である。高βと高熱効率は、競争力のあるCOEを達成するための最も効果的なパラメータである。高効率発電所を達成するために、高い熱効率(η = 41%)を可能にする過熱蒸気サイクルが採用された。電流分布制御と中性粒子ビーム電流駆動による高速プラズマ回転は、理想MHD活動をトロイロン係数βN = 5.5まで安定化する。コスト評価により、CRESTは競争力のあるコストで約1.16GW(e)の電力を生成できることが示された。

装置

iter中精度(概要文一致)

wiki

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

関連論文

Study of a compact reversed shear Tokamak reactor

1998Fusion Engineering and Design

Thermal-hydraulic design of direct superheated steam blanket for the compact reversed shear tokamak reactor (CREST)

2001Fusion Engineering and Design

Conceptual design of a breeding blanket with super-heated steam cycle for CREST-1

2000Fusion Engineering and Design

A cost minimized tokamak reactor using conservative coils/cooling technology

1998Fusion Engineering and Design

Study of design parameters for minimizing the cost of electricity of tokamak fusion power reactors

1998Nuclear Fusion

Development path of low aspect ratio tokamak power plants

1998Fusion Engineering and Design

Analysis of critical development issues towards advanced tokamak power plant CREST

2007Nuclear Fusion

Toroidal reactor designs as a function of aspect ratio and elongation

2002Nuclear Fusion

The optimisation of the STEP electron cyclotron current drive concept

2024Nuclear Fusion

Demonstration tokamak fusion power plant for early realization of net electric power generation

2005Nuclear Fusion