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

Russian DEMO plant study

Yu.A. Sokolov, I.V. Altovskij, A.A. Borisov, A.A. Grigor’yan, V.F. Zubarev1998年Fusion Engineering and DesignIF 1.7出版社

AbstractA conceptual design study of the DEMO reactor is being carried out in Russia. The main efforts are concentrated on the study of steady state reactor DEMO-S. This reactor will be operated with an advanced plasma regime involving a high fraction of bootstrap current. A divertor concept with open liquid lithium as a plasma facing material was chosen. Two extreme approaches were analyzed: the first assumes that liquid lithium is loaded with direct heat flux from 100 to 150 MW m−2; the consumption of liquid lithium and a form of lithium surface are defined; in the second approach lithium plasma dynamics in the divertor is analysed using the 2-D MHD divertor code. With this approach heat loads are considerably decreased by the radiation. Some additional issues connected with utilization of vanadium alloys in the DEMO reactor, including environmental and safety aspects, material activation and refabrication were also analyzed.

日本語訳

DEMO炉の概念設計研究がロシアで実施されている。主な取り組みは、定常運転炉DEMO-Sの研究に集中している。この炉は、高いブートストラップ電流割合を伴う先進プラズマ運転モードで運転される予定である。プラズマ対向材料として開放型液体リチウムを用いたダイバータ概念が選択された。2つの極端なアプローチが分析された:第一に、液体リチウムが100〜150 MW m−2の直接熱流束を受けると仮定し、液体リチウムの消費量とリチウム表面の形状が定義された;第二に、2次元MHDダイバータコードを用いてダイバータ内のリチウムプラズマ動力学が解析された。このアプローチにより、放射によって熱負荷が大幅に低減される。さらに、DEMO炉におけるバナジウム合金の利用に関連するいくつかの課題、すなわち環境・安全性の側面、材料の放射化、再加工についても分析された。

wiki

DEMO
この論文にはまだAI要約がありません。

関連論文

Liquid lithium divertor system for fusion reactor

2009Fusion Engineering and Design

Energy removal and MHD performance of lithium capillary-pore systems for divertor target application

2000Fusion Engineering and Design

Lithium divertor concept and results of supporting experiments

2002Plasma Physics and Controlled Fusion

A physical model of an ejection suppressed CPS liquid lithium divertor target

2015Nuclear Fusion

Nuclear analysis of the Water cooled lithium lead DEMO reactor

2020Fusion Engineering and Design

Li3: first step studies of a liquid lithium limiter

2002Fusion Engineering and Design

Power handling and vapor shielding of pre-filled lithium divertor targets in Magnum-PSI

2019Nuclear Fusion

Plasma equilibrium reconstructions in the lithium tokamak experiment

2012Nuclear Fusion

A novel liquid lithium jet-cooled finger-type divertor target concept for fusion power plant application

2021Nuclear Fusion

Recent progress in the NSTX/NSTX-U lithium programme and prospects for reactor-relevant liquid-lithium based divertor development

2013Nuclear Fusion