Author/Authors :
Veredas، نويسنده , , G. and Fradera، نويسنده , , J. and Fernلndez، نويسنده , , I. and Batet، نويسنده , , L. and Peٌalva، نويسنده , , I. and Mesquida، نويسنده , , L. and Abellà، نويسنده , , J. and Sempere، نويسنده , , J. and Martيnez، نويسنده , , I. and Herrazti، نويسنده , , B. and Sedano، نويسنده , , L.، نويسنده ,
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.
Keywords :
Tritium recovery , Tritium breeding , Tritium self-sufficiency , Permeator