Abstract
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.
Original language | English |
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Pages (from-to) | 1054-1058 |
Number of pages | 5 |
Journal | Fusion Science and Technology |
Volume | 41 |
Issue number | 3 II |
DOIs | |
Publication status | Published - May 2002 |
All Science Journal Classification (ASJC) codes
- Civil and Structural Engineering
- Nuclear and High Energy Physics
- Nuclear Energy and Engineering
- Materials Science(all)
- Mechanical Engineering