Carbon–Carbon Composite Materials

Data are summarized on the performance characteristics and properties of Russian-produced and foreign carbon–carbon composite materials for various engineering applications. The effect of neutron irradiation on their macroscopic properties and structure is examined. The relationships between the radiation-induced dimensional changes and properties of the composites are established, which can be used in assessing the engineering performance and optimizing the fabrication of carbon–carbon composites.     

Radiation Resistance of a Graphite–Fluoroplastic Antifriction Material

Experimental data are presented on the effect of gamma and neutron irradiations on the properties of a graphite–fluoroplastic antifriction material.     

Criterion for the Engineering Performance of Carbon Materials under Neutron Irradiation

A criterion is proposed for the engineering performance of graphite in graphite–uranium reactors. The criterion is based on the ratio of the compressive strength to the flexural strength, which are periodically determined by testing cores cut from the brickwork of the reactors in service. The factors influencing this parameter are analyzed.