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Conference Article: Engineering thermomechanics of nuclear graphites under neutron irradiation, oxidation and transient heat up: A review

Abstract

Structural assessment of a GCR graphite component involves thermal and stress/strain calculations to determine local stress states. These analyses require data base and predictive models on thermomechanical behavior of graphite materials. The paper reviews state-of-the-art of graphite technology on thermomechanics with emphasis on nonisothermal irradiation, nonuniform oxidation and post-irradiation annealing. Relevant data base and predictive models are discussed. Nonisothermal irradiation behavior have now been handled partly by use of the Graphite Damage Model. Further verification of the methodology is being attempted. Some data base and analyses on deformation behavior of nonuniformly oxidized specimens are available. A few experimental evidences suggest that among various thermomechanical properties thermal conductivity should influence transient heatups after irradiations. Current knowledge and additional key data may be coordinated with a further sophistication of descriptive models for better performance and reliable operation of graphite components in actual reactors.

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Reference:

Specialists' meeting on the status of graphite development for gas cooled reactors. Tokai, Ibaraki (Japan). 9-12 Sep 1991

International Atomic Energy Agency, Vienna (Austria)

IAEA-TECDOC--690, pp:195-199