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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.
| Original language | English |
|---|---|
| Pages (from-to) | 18-28 |
| Number of pages | 11 |
| Journal | Journal of Nuclear Materials |
| Volume | 499 |
| Early online date | 8 Nov 2017 |
| DOIs | |
| Publication status | Published - 1 Feb 2018 |
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Dive into the research topics of 'Modelling deformation and fracture of Gilsocarbon graphite subject to service environments'. Together they form a unique fingerprint.Projects
- 1 Finished
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UNIGRAF - Understanding and improving graphite for nuclear fission
Flewitt, P. E. J. (Principal Investigator)
31/08/15 → 28/02/19
Project: Research
Equipment
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