Graphite for helium-cooled reactors. A review

Abstract

This review encompasses information on the manufacture of nuclear graphites, including the improved i s o t r o p i c grades, the phy sicaZ, chemical, and morpho logical differences among these materials, the theory of radiationinduced changes as influenced by morphology, and available data on radiationinduced changes i n dimensions, physical properties, and chemical r e a c t i v i t y . The review a l s o includes information on neutron dosimetry, carbon displacement cross sections, and the general problem of transposing data from one reactor t o m o t h e r . I n lesser d e t a i l , information on other materials, such as boron carbide, non-graphitized carbons, cmd py r o ly t i c carbon coatings, i s reviewed w i t h respect t o possible use and performance i n a HTGR.