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Mass-Transport Properties to Estimate Rates of Tritium Recovery from Flibe Blanket

Satoshi Fukada, Masabumi Nishikawa, Akio Sagara, Takayuki Terai

Fusion Science and Technology / Volume 41 / Number 3P2 / May 2002 / Pages 1054-1058

Blanket Material and Process / Proceedings of the Sixth International Conference on Tritium Science and Technology Tsukuba, Japan November 12-16, 2001 /

Rates of the recovery of tritium from a blanket of a fusion reactor with a 1 GWt power are estimated. The recovery methods are a permeation window, a Flibe-He counter-current-extraction tower and a rotational centrifugal flow system. There is high possibility in that the rate-determining step of the permeation window is tritium diffusion in Flibe. The tritium diffusion in liquid Flibe drops is also the dominant process in the counter-current-extraction tower. The determination of the tritium diffusion rate in purified or unpurified Flibe (or actual blanket environment) is a key to estimate the tritium recovery rate accurately.

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