Modelling deformation and fracture of Gilsocarbon graphite subject to service environments
B. Savija (TU Delft - Materials and Environment)
G.M. Smith (HH Wills Physics Laboratory)
P. J. Heard (HH Wills Physics Laboratory)
Eleni Sarakinou (HH Wills Physics Laboratory)
J. E. Darnbrough (HH Wills Physics Laboratory)
K. R. Hallam (HH Wills Physics Laboratory)
H.E.J.G. Schlangen (TU Delft - Materials and Environment)
Peter E.J. Flewitt (HH Wills Physics Laboratory, University of Bristol)
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Abstract
Commercial graphites are used for a wide range of applications. For example, Gilsocarbon graphite is used within the reactor core of advanced gas-cooled reactors (AGRs, UK) as a moderator. In service, the mechanical properties of the graphite are changed as a result of neutron irradiation induced defects and porosity arising from radiolytic oxidation. In this paper, we discuss measurements undertaken of mechanical properties at the micro-length-scale for virgin and irradiated graphite. These data provide the necessary inputs to an experimentally-informed model that predicts the deformation and fracture properties of Gilsocarbon graphite at the centimetre length-scale, which is commensurate with laboratory test specimen data. The model predictions provide an improved understanding of how the mechanical properties and fracture characteristics of this type of graphite change as a result of exposure to the reactor service environment.
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