Carbon transport, deposition and fuel accumulation in castellated structures exposed in TEXTOR
2007 (English)In: Journal of Nuclear Materials, ISSN 0022-3115, E-ISSN 1873-4820, Vol. 367, 1481-1486 p.Article in journal (Refereed) Published
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 a]., 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 similar to 0.03% of the impinging D-fluence. Modeling was performed to simulate carbon transport into the gaps.
Place, publisher, year, edition, pages
2007. Vol. 367, 1481-1486 p.
asdex upgrade, diii-d, retention, deuterium, tokamak, tiles, jet
Fusion, Plasma and Space Physics
IdentifiersURN: urn:nbn:se:kth:diva-16912DOI: 10.1016/j.jnucmat.2007.04.029ISI: 000249083500106ScopusID: 2-s2.0-34447559896OAI: oai:DiVA.org:kth-16912DiVA: diva2:334955
QC 201311202010-08-052010-08-052013-11-20Bibliographically approved