AI要約装置ジャーナル ChatGPT About

© 2026 FUSIONPAPERS

About 法務情報

トップに戻る

Control of tritium in FFHR-2 self-cooled Flibe blanket

Satoshi Fukada, Akio Morisaki, Akio Sagara, Takayuki Terai2006年Fusion Engineering and DesignIF 1.7 出版社

この論文にはまだAI要約がありません。

関連論文

Plentiful Tritium generation by a FFHR to feed a fusion power plant with simplified blanket

2025Fusion Engineering and Design

Study of safety concept for a helical-type fusion reactor, FFHR

1998Fusion Engineering and Design

Study on the temperature control mechanism of the tritium breeding blanket for CFETR

2017Nuclear Fusion

Design and development of the Flibe blanket for helical-type fusion reactor FFHR

2000Fusion Engineering and Design

Effects of simultaneous transfer of heat and tritium through Li–Pb or Flibe blanket

2010Fusion Engineering and Design

Tritium transport in the water cooled Pb17Li blanket concept of DEMO

1991Fusion Engineering and Design

Initial studies of tritium behavior in flibe and flibe-facing material

2002Fusion Engineering and Design

Aqueous salt blanket tritium concentration control by water storage

1990Fusion Engineering and Design

The role of a blanket tritium system on the fusion fuel cycle

1989Fusion Engineering and Design

Some considerations on tritium control for the European ceramic BIT DEMO blanket

1991Fusion Engineering and Design

Control of tritium in FFHR-2 self-cooled Flibe blanket — 核融合論文 — FusionPapers