Ceramic materials for fusion reactors

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Abstract
Materials studies have identified siliconized silicon carbide as the most promising material. It has a long-term service limit of 1200/sup 0/C and can be fabricated in large shapes. Its strength and Weibull modulus do not decrease significantly at 1200/sup 0/C after fast neutron irradiation up to a fluence of 1.2 x 10/sup 25/ n/m/sup 2/. However, its thermal conductivity is reduced markedly during irradiation. Laboratory tests show that this affects the thermal shock resistance of silicon carbide adversely. How this will change the design of silicon carbide first walls remains to be evaluated.

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