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Use of carbon and graphite materials in high temperature gas-cooled reactors, Structural design issues on carbon and graphite materials for nuclear reactors, Application of C/C composite materials to nuclear field

Ishihara, Masahiro 

Books summarizing the basic contents of nuclear carbon and graphite materials are seen in overseas, however, there is no book describing the whole aspect of the materials in Japan. Therefore, we describe fundamental matters on the materials in a wide range from basic to application. Here, we include also technical information necessary for structural design and structural integrity evaluation of the materials used in the graphite-moderated high temperature helium gas-cooled reactor. This is an introduction useful for students and graduate students, researchers and engineers, and experts who want to learn the whole issues of the materials for high temperature gas-cooled reactor.

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