Author/Authors :
Litnovsky، نويسنده , , A. and Philipps، نويسنده , , V. and Kirschner، نويسنده , , A. and Wienhold، نويسنده , , P. and Sergienko، نويسنده , , G. and Kreter، نويسنده , , A. and Samm، نويسنده , , U. and Schmitz، نويسنده , , O. and Krieger، نويسنده , , K. and Karduck، نويسنده , , P. and Blome، نويسنده , , M. and Emmoth، نويسنده , , B. and Rubel، نويسنده , , M. L. Breuer، نويسنده , , U. and Scholl، نويسنده , , A.، نويسنده ,
Abstract :
In order to maintain the thermo-mechanical durability of ITER it is proposed to castellate the interior surface of the first wall and divertor by splitting them into small-size cells [W. Daener et al., Fusion Eng. Des. 61&62 (2002) 61]. A concern is the accumulation of fuel in the gaps of the castellation. In TEXTOR, molybdenum limiters were exposed in the scrape-off layer (SOL) plasma to assess fuel accumulation. The first limiter was exposed under deposition-dominated conditions. Carbon deposits were formed both on top surfaces and in the gaps. About 0.12% of the impinging D-fluence was found in the gaps. Another castellated limiter was exposed under erosion-dominated conditions. Deposited layers were found only on the plasma shadowed areas of the gaps. A significant amount of molybdenum from the limiter was found intermixed in the deposit. The gaps contained ∼0.03% of the impinging D-fluence. Modeling was performed to simulate carbon transport into the gaps.
