Abstract
The fast and efficient recovery of bred tritium represents a major milestone of tritium breeding technologies R&D and is key for the demonstration of fusion reactor fuel self-sufficiency. For lead-lithium eutectic, diverse technologies are currently being investigated and qualified. Permeator Against Vacuum (PAV) solution represents a firm candidate because: (i) runs as a single-step process for tritium on-line recovery, (ii) works passively allowing to be thermally governed, (iii) can be easily in-pipe integrated in Pb15.7Li loop systems and (iv) can be conceived with high compactness. An optimal design of a PAV requires a detailed hydraulic design optimization for established operational ranges. An optimal PAV design is proposed and qualified by numerical simulation.
Original language | English |
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Pages (from-to) | 2365-2369 |
Number of pages | 5 |
Journal | Fusion Engineering and Design |
Volume | 86 |
Issue number | 9-11 |
DOIs | |
Publication status | Published - Oct 2011 |
Event | 26th Symposium on Fusion Technology (SOFT-26) - Porto - Portugal, Porto , Portugal Duration: 27 Sept 2010 → 1 Oct 2010 Conference number: 26 |
Keywords
- Permeator
- Tritium breeding
- Tritium recovery
- Tritium self-sufficiency