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

A preliminary assessment of beryllium dust oxidation during a wet bypass accident in a fusion reactor

Brad J. Merrill, Richard L. Moore, J. Phillip Sharpe2009年Fusion Engineering and DesignIF 1.7 出版社

wiki

この論文にはまだAI要約がありません。

関連論文

Beryllium R&D for fusion applications

2000Fusion Engineering and Design

Chemical reactivity and mobilization of beryllium exposed to steam

1997Fusion Engineering and Design

Oxidation of beryllium—a scanning Auger investigation

2005Nuclear Fusion

A review of dust in fusion devices: Implications for safety and operational performance

2002Fusion Engineering and Design

Novel plasma source for safe beryllium spectral line studies in the presence of beryllium dust

2018Review of Scientific Instruments

A review on irradiated beryllium and beryllium alloy for fusion reactor application: Microstructure evolution, properties changes, and fabrication

2025Fusion Engineering and Design

Beryllium as the plasma-facing material in fusion energy systems—experiments, evaluation, and comparison with alternative materials

1997Fusion Engineering and Design

Helium induced swelling and tritium trapping mechanisms in irradiated beryllium: a comprehensive approach

1995Fusion Engineering and Design

High dose neutron irradiation damage in beryllium as blanket material

2001Fusion Engineering and Design

Real-time measurement of hydrogen generation level during beryllium dust oxidation by steam depending on the dust arrangement geometry

2006Fusion Engineering and Design