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

Parametric thermal-hydraulic analysis of the EU DEMO Water-Cooled Lithium-Lead First Wall using the GETTHEM code

A. Froio, A. Del Nevo, E. Martelli, L. Savoldi, R. Zanino2018年Fusion Engineering and DesignIF 1.7 出版社

wiki

DEMO Lithium First wall Thermal-hydraulics

この論文にはまだAI要約がありません。

関連論文

Parametric study of the influence of First Wall cooling water on the Water Cooled Lithium Lead Breeding Blanket nuclear response

2019Fusion Engineering and Design

Thermal-hydraulic modeling and analyses of the water-cooled EU DEMO using RELAP5 system code

2019Fusion Engineering and Design

Development of a thermal-hydraulic model of the EU-DEMO Water Cooled Lithium Lead Breeding Blanket Primary Heat Transport System

2023Fusion Engineering and Design

Thermal-hydraulic design of water cooled first wall of the fusion reactor under DEMO conditions

2017Fusion Engineering and Design

Parametric thermal-hydraulic analysis of the DEMO PF coils designed by CEA during the breakdown phase

2023Fusion Engineering and Design

Optimization of the first wall for the DEMO water cooled lithium lead blanket

2015Fusion Engineering and Design

Nuclear analysis of the Water cooled lithium lead DEMO reactor

2020Fusion Engineering and Design

Parametric FE model for the thermal and hydraulic optimization of a Plasma Facing Component equipped with sacrificial lattice armours for First Wall limiter application in EU-DEMO fusion reactor

2023Fusion Engineering and Design