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

Molten salts in fusion nuclear technology

H Moriyama, A Sagara, S Tanaka, R.W Moir, D.K Sze1998年Fusion Engineering and DesignIF 1.7出版社

AbstractIn the field of fusion nuclear technology, much interest lies in the use of molten salts. In some innovative design studies, the use of molten fluoride, especially the LiF–BeF2 mixture called Flibe, has been suggested as the primary loop coolant because of its inherent advantages such as high temperature stability and low electrical conductivity. The use of molten salts has also been suggested for the chemical processing of tritium. Together with the physical and chemical properties of molten salts, recent studies on the use of molten salts in fusion nuclear technology are reviewed and discussed, and issues are addressed for successful future development.

日本語訳

核融合技術の分野において、溶融塩の利用には大きな関心が寄せられている。いくつかの革新的な設計研究では、溶融フッ化物、特にFlibeと呼ばれるLiF–BeF₂混合物を、高温安定性や低電気伝導性といった固有の利点から、一次系冷却材として使用することが提案されている。また、溶融塩はトリチウムの化学処理にも利用が提案されている。本稿では、溶融塩の物理的・化学的特性とともに、核融合技術における溶融塩の利用に関する最近の研究を概説し、考察を加えるとともに、今後の発展に向けた課題について論じる。

この論文にはまだAI要約がありません。

関連論文

Molten salts evaluation for application in the fusion power plant's intermediate heat transfer system

2023Fusion Engineering and Design

Experimental research on molten salt thermofluid technology using a high-temperature molten salt loop applied for a fusion reactor Flibe blanket

2002Fusion Engineering and Design

Combined gettering and molten salt process for tritium recovery from lithium

1989Fusion Engineering and Design

Advancing tritium self-sufficiency in fusion power plants: insights from the BABY experiment

2025Nuclear Fusion

Localization, hopping, and diffusion of electrons in molten salts

1987PHYSICAL REVIEW LETTERS

Nuclear aspects of molten salt blankets

2003Fusion Engineering and Design

The logic behind thick, liquid-walled, fusion concepts

1995Fusion Engineering and Design

Symbiotic system of a fusion and a fission reactor with very simple fuel reprocessing

1978Nuclear Fusion

Selective electromagnetic induction heating of metal particles in molten salt for tritium extraction: A systematic numerical investigation

2021Fusion Engineering and Design

Numerical analysis of the viscosity of ZrF4–BeF2 molten salts for nuclear transmutation using fusion neutron sources

2024Fusion Engineering and Design