Abstract
Graphite has been selected as a structural material in HTR plants because of its favourable characteristics. The low ductility and the low tensile strength of this material as well as its behaviour under the impact of fast neutron irradiation require special construction directives and design criteria. It is demonstrated that by an appropriate structural design it is possible to separate the tasks and functions of the individual graphite components, which permits a classification of each component into one of three classes of qualitity assurance. Adequate stress criteria have been developed for the graphite internals of HTR based on probabilistic methods.
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