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

Design and qualification of an on-line permeator for the recovery of tritium from lead–lithium eutectic breeding alloy

G. Veredas, J. Fradera, I. Fernández, L. Batet, L. Sedano2011年Fusion Engineering and DesignIF 1.7出版社

wiki

TritiumLithiumLead-lithium eutectic
この論文にはまだAI要約がありません。

関連論文

Design of a permeator against vacuum for tritium extraction from eutectic lithium-lead in a DCLL DEMO

2017Fusion Engineering and Design

Experimental design of tritium extraction loop from lead lithium eutectic

2010Fusion Engineering and Design

Low tritium partial pressure permeation system for mass transport measurement in lead lithium eutectic

2016Fusion Engineering and Design

Evaluation of the response time of H-concentration probes for tritium sensors in lead–lithium eutectic alloy

2014Fusion Engineering and Design

Interaction of tritium and helium with lead–lithium eutectic under reactor irradiation

2014Fusion Engineering and Design

Tritium transport modeling at system level for the EUROfusion dual coolant lithium-lead breeding blanket

2017Nuclear Fusion

Recent experimental results of the rates of hydrogen permeation through metallic materials in the presence of liquid pb17li alloy: Influence on the performance and design of tritium recovery equipment

1989Fusion Engineering and Design

Development of advanced hydrogen permeation sensors to measure Q2 concentration in lead-lithium eutectic alloy

2017Fusion Engineering and Design

Combined gettering and molten salt process for tritium recovery from lithium

1989Fusion Engineering and Design

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

1991Fusion Engineering and Design