Abstract
Graphite materials are widely used as plasma facing components for major fusion devices such as TFTR, JET and JT-60, because of their low Z and good high temperature characteristics. However, for their further application in near and middle term machines a comprehensive evaluation has to be undertaken, including vacuum properties, fracture toughness under normal and off-normal conditions, hydrogen recycling, erosion, retention of tritium and effects of radiation by 14 MeV neutrons. The present status of the data base for each item is presented and discussed on the basis of graphite chemistry and physics. Another issue to be considered is the design of plasma facing component such as tile attachment, active cooling capability, etc. These considerations are extremely important for the next generation fusion machines such as ITER.
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