Graphite is selected as moderator, reflector and major internal structural material in high temperature gas-cooled reactors (HTRs) because of its unique characteristics. Inside the core, both high temperature and fast neutron irradiation can influence the mechanical property, thermal property, dimensional change and some other characteristics of graphite in evidence, while the creep of graphite plays an important role in the whole process. There have been several kinds of creep models, and the creep process is divided into two parts in most of models: primary creep and secondary creep. The primary is always treated as exponential function while the secondary is linear. A code based on user subroutines of MSC.MARC is developed in INET in order to perform three-dimensional finite element analysis of irradiation behavior of the graphite components for the HTRs. In this paper, the irradiation behavior of nuclear graphite was simulated, and the impact of irradiation-induced deformation of various kinds of graphite on the irradiation-induced stresses and lives is discussed. In order to describe the creep behavior, the linear elastic model is chosen while the influence of high temperature and irradiation to the dimensional change, physical parameters and creep property of nuclear graphite is used as original data.
- Nuclear Engineering Division
Effect of Irradiation Deformation and Graphite Varieties on the Irradiation Equivalent Stress and Life of Nuclear Graphite
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Fang, X, Wang, H, & Yu, S. "Effect of Irradiation Deformation and Graphite Varieties on the Irradiation Equivalent Stress and Life of Nuclear Graphite." Proceedings of the 18th International Conference on Nuclear Engineering. 18th International Conference on Nuclear Engineering: Volume 5. Xi’an, China. May 17–21, 2010. pp. 697-700. ASME. https://doi.org/10.1115/ICONE18-30359
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