Modelling deformation and fracture of Gilsocarbon graphite subject to service environments

Branko Šavija*, Gillian E. Smith, Peter J. Heard, Eleni Sarakinou, James E. Darnbrough, Keith R. Hallam, Erik Schlangen, Peter E.J. Flewitt

*Corresponding author for this work

Research output: Contribution to journalArticle (Academic Journal)peer-review

5 Citations (Scopus)
255 Downloads (Pure)

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.

Original languageEnglish
Pages (from-to)18-28
Number of pages11
JournalJournal of Nuclear Materials
Volume499
Early online date8 Nov 2017
DOIs
Publication statusPublished - 1 Feb 2018

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