Understanding fracture behaviour of PGA reactor core graphite: perspective

R Moskovic, Peter E J Flewitt, E Schlangen, G Smith, AG Crocker, A Hodgkins, Peter J Heard, MR Wootton

Research output: Contribution to journalArticle (Academic Journal)peer-review

Abstract

Magnox reactors are cooled by carbon dioxide gas. The pile grade A (PGA) graphite moderator bricks in the reactor core loose mass and become more porous during service due to the radiolytic oxidation caused by energy deposition, mainly gamma radiation. In addition, neutron irradiation brings about strengthening by irradiation hardening and dimensional change. In this perspective, experimental data related to the attendant microstructural changes and the associated initiation and propagation of cracks within the graphite are revisited. These results are compared with the predictions of multiscale finite element modelling based upon an idealised microstructure. The discussion considers the quasi-brittle characteristics of the PGA graphite over a range of service exposure conditions.
Original languageEnglish
Pages (from-to)129-145
Number of pages17
JournalMaterials Science and Technology
Volume30
Issue number2
DOIs
Publication statusPublished - Feb 2014

Keywords

  • PGA graphite
  • Microstructure
  • Neutron Irradiation
  • Strength
  • Quasi-brittle fracture

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