Carbon transport, deposition and fuel accumulation in castellated structures exposed in TEXTOR

详细信息    查看全文

• 作者：A. Litnovsky ; V. Philipps ; A. Kirschner ; P. Wienhold ; G. Sergienko ; A. Kreter ; U. Samm ; O. Schmitz ; K. Krieger ; P. Karduck ; M. Blome ; B. Emmoth ; M. Rubel ; U. Breuer ; A. Scholl
• 关键词：Glasses ; Mechanical properties ; Crack growth
• 刊名：Journal of Nuclear Materials
• 出版年：2007
• 出版时间：1 August 2007
• 年：2007
• 卷：367-370
• 期：Complete
• 页码：1481-1486
• 全文大小：776 K

文摘

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.