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

Sensitivity study on tritium transport in water cooled solid blanket of China Fusion Engineering Test Reactor

Yuanjie Li, ChaoWei Mai, Xudong Yu, Yang Xiang, Wanli Yang2018年Fusion Engineering and DesignIF 1.7出版社

wiki

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

関連論文

Tritium control modelling for a helium cooled lithium–lead blanket of a fusion power reactor

2006Fusion Engineering and Design

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

2017Nuclear Fusion

Tritium-producing blanket for fusion engineering facility

1989Fusion Engineering and Design

Research and development of the tritium recovery system for the blanket of the fusion reactor in JAEA

2009Nuclear Fusion

Evaluation of tritium production rate in a gas-cooled reactor with continuous tritium recovery system for fusion reactors

2013Fusion Engineering and Design

Development of 3D simulation demonstration platform for tritium safety confinement of China fusion engineering test reactor

2026Fusion Engineering and Design

A water cooled, lithium lead breeding blanket for a DEMO fusion reactor

1991Fusion Engineering and Design

Progress of fusion fuel processing system development at the Japan Atomic Energy Research Institute

2000Fusion Engineering and Design

Tritium issues to be solved for establishment of a fusion reactor

2012Fusion Engineering and Design

Tritium control in fusion reactor materials: A model for Tritium Extracting System

2015Fusion Engineering and Design