Finite element models currently used for predicting irradiation creep and failure of nuclear graphite are presented. The underlying material properties required for these analyses and the relevant property changes due to irradiation are reviewed, followed by a description of the generation of constitutive equations. Continuum damage mechanics-based approaches for predicting the cracking and failure of graphite components are assessed. The computational implementation of the different models is briefly discussed and some examples from published literature are highlighted. To conclude, areas are identified that shall be addressed in order to develop a unified multi-scale continuum damage material behaviour model for graphite as part of the ongoing EPSRC 'Fundamentals of current and future uses of Nuclear Graphite' project.
|Title of host publication||Modelling and Measuring Reactor Core Graphite Properties and Performance - British Carbon Group Conference|
|Place of Publication||Birmingham, UK|
|Publication status||Published - 2011|
|Event||Modeling and Measuring Reactor Core Graphite Properties and Performance - Birmingham, United Kingdom|
Duration: 1 Nov 2011 → 3 Nov 2011
|Conference||Modeling and Measuring Reactor Core Graphite Properties and Performance|
|Period||1/11/11 → 3/11/11|