TY - JOUR
T1 - Modelling deformation and fracture of Gilsocarbon graphite subject to service environments
AU - Savija, B.
AU - Smith, Gillian E.
AU - Heard, Peter J.
AU - Sarakinou, Eleni
AU - Darnbrough, James E.
AU - Hallam, Keith R.
AU - Schlangen, Erik
AU - Flewitt, Peter E.J.
PY - 2018/2/1
Y1 - 2018/2/1
N2 - 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.
AB - 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.
UR - http://www.scopus.com/inward/record.url?scp=85034072999&partnerID=8YFLogxK
U2 - 10.1016/j.jnucmat.2017.10.076
DO - 10.1016/j.jnucmat.2017.10.076
M3 - Article
AN - SCOPUS:85034072999
SN - 0022-3115
VL - 499
SP - 18
EP - 28
JO - Journal of Nuclear Materials
JF - Journal of Nuclear Materials
ER -