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

Development of thermal-hydraulic analysis methodology for multiple modules of water-cooled breeder blanket in fusion DEMO reactor

Geon-Woo Kim, Jeong-Hun Lee, Hyoung-Kyu Cho, Goon-Cherl Park, Kihak Im2016年Fusion Engineering and DesignIF 1.7出版社

wiki

DEMOBreeder blanketThermal-hydraulics
この論文にはまだAI要約がありません。

関連論文

Design and technology development of solid breeder blanket cooled by supercritical water in Japan

2003Nuclear Fusion

Structure optimization of helium-cooled blanket for fusion reactor based on three-dimensional full-scale thermal-hydraulic analysis

2023Fusion Engineering and Design

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

2017Fusion Engineering and Design

Thermal-hydraulic design of water-cooled pressure tube blanket for a fusion driven subcritical reactor

2013Fusion Engineering and Design

Thermal-hydraulics design and analysis on a helium-cooled high power density blanket for a fusion–fission hybrid reactor

2010Fusion Engineering and Design

Thermal-hydraulic modeling and analysis of the Water Cooling System for the ITER Test Blanket Module

2020Fusion Engineering and Design

Thermal-hydraulic analysis on the whole module of water cooled ceramic breeder blanket for CFETR

2016Fusion Engineering and Design

A review of thermal hydraulics systems analysis for breeding blanket design and future needs for fusion engineering demonstration facility design and licensing

2021Fusion Engineering and Design

Impact of helium working pressure on the thermal-hydraulic performance of FW/Blanket for fusion reactor

2024Fusion Engineering and Design

A conceptual design study of a reversed field pinch fusion reactor

1989Fusion Engineering and Design