高温ガス炉用黒鉛の機械的性質

抄録

A review is presented of recent results obtained by many investigators in this field concerning the mechanical properties of graphites intended for use in high temperature gas-cooled reactors, with particular reference to the important properties related to the structural design of graphite sleeves and graphite blocks in the reactor core. Firstly, problems in the design of the structural components of the core and the properties thereof are reviewed. Then the static mechanical properties such as stress-strain curves, elastic modulus and strength are examined, followed by a description of the irradiation creep behavior and discussion on the statistical treatment of strength and fatigue. Data are given on the essential properties required in the core design. It is noted in particular that the statistical nature of strength and fatigue offers important bases for determining design criteria, such as allowable stress. As yet, the data available on irradiation creep, strength and fatigue are not sufficient, and further studies are being planned for the future.