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

Study on melting and solidification behaviors of tungsten loaded by high heat flux for divertor in tokamak fusion reactor

Eiji Hoashi, Shinpei Kuroyanagi, Takafumi Okita, Takeru Maeji, Yoshio Ueda2018年Fusion Engineering and DesignIF 1.7出版社

wiki

DivertorTungsten
この論文にはまだAI要約がありません。

関連論文

In-situ measurement of surface modifications of tungsten exposed to pulsed high heat flux for divertor design in tokamak-type fusion nuclear reactors

2020Fusion Engineering and Design

Thermofluid analysis of free surface liquid divertor in tokamak fusion reactor

2002Fusion Engineering and Design

Effects of nitrogen-seeded deuterium plasma on tungsten surfaces

2019Nuclear Fusion

Development of tungsten armored high heat flux plasma facing components for ITER like divertor application

2019Fusion Engineering and Design

Baseline high heat flux and plasma facing materials for fusion

2017Nuclear Fusion

Operating a full tungsten actively cooled tokamak: overview of WEST first phase of operation

2022Nuclear Fusion

High-temperature plasmas in a tokamak fusion test reactor

1987PHYSICAL REVIEW LETTERS

Characterization of the in situ leading-edge-induced melting on the ITER-like tungsten divertor in EAST

2020Nuclear Fusion

Synchronized fusion development considering physics, materials and heat transfer

2017Nuclear Fusion

Development of a high-heat flux cooling element with potential application in a near-term fusion power plant divertor

2015Fusion Engineering and Design