Projects per year
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 |
Fingerprint
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
-
UNIGRAF - Understanding and improving graphite for nuclear fission
Flewitt, P. E. J. (Principal Investigator)
31/08/15 → 28/02/19
Project: Research