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 preliminary analyses of the new Water Cooled Lithium Lead TBM for ITER

J. Aubert, G. Aiello, D. Alonso, T. Batal, J. Vallory2020年Fusion Engineering and DesignIF 1.7出版社

装置

iter高精度(タイトル一致)

wiki

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

関連論文

Alternative design of DEMO Water Cooled Lithium Lead internal structure

2019Fusion Engineering and Design

Results of lead-lithium ceramic breeder TBM conceptual design optimization

2014Fusion Engineering and Design

Nuclear analysis of the Water cooled lithium lead DEMO reactor

2020Fusion Engineering and Design

Development of the water cooled lithium lead blanket for DEMO

2014Fusion Engineering and Design

Preliminary design of the top cap of DEMO Water-Cooled Lithium Lead breeding blanket segments

2020Fusion Engineering and Design

Design of a System for Hydrogen isotopes Injection into Lead-Lithium

2018Fusion Engineering and Design

Thermophysical properties and thermodynamic equation of state of lithium-lead for nuclear fusion reactor safety calculations

2025Nuclear Fusion

Neutronic analysis for the EU water-cooled lithium–lead test blanket module in ITER-FEAT

2005Nuclear Fusion

Preliminary experimental study of liquid lithium water interaction

2015Fusion Engineering and Design

Neutronic, thermal–hydraulic and stress analysis of RF lithium cooled test blanket module for ITER

2000Fusion Engineering and Design