Models of bending strength for Gilsocarbon graphites irradiated in inert and oxidising environments

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 cons...

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Published in:Journal of nuclear materials 2013-05, Vol.436 (1-3), p.208-216
Main Authors: Eason, Ernest D., Hall, Graham N., Marsden, Barry J., Heys, Graham B.
Format: Article
Language:English
Subjects:
AGR
Bend strength
Calibration
Fast neutrons
Inert
Irradiation
Oxidation
Strength
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creator Eason, Ernest D.
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description 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.
doi_str_mv 10.1016/j.jnucmat.2012.06.034
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subjects AGR
Bend strength
Calibration
Fast neutrons
Inert
Irradiation
Oxidation
Strength
title Models of bending strength for Gilsocarbon graphites irradiated in inert and oxidising environments
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