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Recent experimental results of the rates of hydrogen permeation through metallic materials in the presence of liquid pb17li alloy: Influence on the performance and design of tritium recovery equipment

A. Viola, P.L. Lolli-Ceroni, G. Pierini1989年Fusion Engineering and DesignIF 1.7出版社

The utilization of the Pb-17Li eutectic as a breeding material for a D-T fusion reactor is limited by problems related to the tritium permeation from the blanket to the water-cooling system and to the environment.Experimental work is being carried out to determine the kinetics of the rates of hydrogen mass transfer through metallic walls wetted by the eutectic. The experimental results have shown a permeation rate which is much lower than that so far considered in the feasibility study.

日本語訳

D-T核融合炉の増殖材としてのPb-17Li共晶の利用は、ブランケットから水冷却系および環境へのトリチウム透過に関連する問題によって制限されている。共晶に濡れた金属壁を通る水素の質量移動速度の速度論を決定するために実験研究が実施されている。実験結果は、実現可能性調査においてこれまで考慮されてきたものよりもはるかに低い透過速度を示した。

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TritiumTritium recovery
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