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Models of bending strength for Gilsocarbon graphites irradiated in inert and oxidising environments
Eason, Ernest D; Hall, Graham N; Marsden, Barry J; Heys, Graham B
Journal of Nuclear Materials. 2013;436(1):208-216.
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Abstract
This paper presents the development and validation of an empirical model of fast neutron damage and radiolytic oxidation effects on bending strength for the moulded Gilsocarbon graphites used in Advanced Gas-cooled Reactors (AGRs). The inert environment model is based on evidence of essentially constant strength as fast neutron dose increases in inert environment. The model of combined irradiation and oxidation calibrates that constant along with an exponential function representing the degree of radiolytic oxidation as measured by weight loss. The change in strength with exposure was found to vary from one AGR station to another. The model was calibrated to data on material trepanned from AGR moderator bricks after varying operating times.
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- Related website http://www.sciencedirect.com/science/article/pii/S0022311512003406