A Review of Current Finite Element Models for Irradiation Creep and Failure of Nuclear Graphite

David W J Tanner, A. A. Becker, W. Sun, T. H. Hyde

Research output: Chapter in Book/Report/Conference proceedingConference Contribution (Conference Proceeding)

Abstract

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.
Original languageEnglish
Title of host publicationModelling and Measuring Reactor Core Graphite Properties and Performance - British Carbon Group Conference
Place of PublicationBirmingham, UK
Publication statusPublished - 2011
EventModeling and Measuring Reactor Core Graphite Properties and Performance - Birmingham, United Kingdom
Duration: 1 Nov 20113 Nov 2011

Conference

ConferenceModeling and Measuring Reactor Core Graphite Properties and Performance
Country/TerritoryUnited Kingdom
CityBirmingham
Period1/11/113/11/11

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