Rules for design of nuclear graphite core components — Some considerations and approaches

• Published in: Nuclear engineering and design Vol. 46; no. 2; pp. 313 - 333
• Main Authors: Svalbonas, V., Stilwell, T.C., Zudans, Z.
• Format: Journal Article
• Language: English
• Published: Elsevier B.V 01.01.1978
• ISSN: 0029-5493; 1872-759X
• DOI: 10.1016/0029-5493(78)90018-3

The use of graphite as a structural element presents unusual problems both for the designer and stress analyst. When the structure happens to be a nuclear reactor core, these problems are significantly magnified both by the environment and the attendant safety requirements. In the high temperature gas reactor (HTGR) core a large number of elements are constructed of nuclear graphite. This paper discusses the attendant difficulties, and presents some approaches, for ASME code safety-consistent design and analysis. The statistical scatter of material properties, which complicates even the definitions of allowable stress, as well as the brittle, anisotropic, inhomogeneous nature of the graphite was considered. The study of this subject was undertaken under contract to the U.S. Nuclear Regulatory Commission.