Ceramic materials for fusion reactors
Ceramic materials for fusion reactors
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聚变反应堆陶瓷材料
DOI：
10.2172/6654697
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发表时间：
1981
期刊：
影响因子：
--
通讯作者：
J. Corelli
中科院分区：
文献类型：
--
作者：
G. Hopkins;G. C. Trantina;J. Corelli
材料研究已经确定硅化碳化硅是最有前途的材料。它的长期使用极限为1200/sup 0/C，可以制造成大形状。在1200/sup 0/C温度下，经1.2 × 10/sup 25/ n/m/sup 2/的快中子辐照后，其强度和Weibull模量没有明显下降。然而，它的热导率在辐照过程中显着降低。实验室测试表明，这对碳化硅的抗热震性产生不利影响。这将如何改变碳化硅第一壁的设计仍有待评估。
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.