Graphite in Gas-Cooled Reactors

B J Marsden, G N Hall

Research output: Contribution to journalArticlepeer-review


When graphite is used in a nuclear reactor, it will undergo dimensional and material properties changes due to the fast neutron irradiation and changes in temperature. These changes are further complicated in air and CO2-cooled reactors due to the effect of radiolytic oxidation. This chapter draws upon the unique experiences in the UK of CO2-cooled reactors and the behavior of graphite within such reactor environments. Examples of the observed changes in UK graphite grades as well as the current understanding of the mechanisms behind the changes are presented.
Original languageEnglish
Pages (from-to)357-421
Number of pages65
JournalReference Module in Materials Science and Materials Engineering
Publication statusPublished - 3 Aug 2020


  • Advanced gas-cooled reactor (AGR); Dimensional change; Fast neutron irradiation; Gilsocarbon; Graphite; High-temperature reactor (HTR); Irradiation creep; Magnox; Material properties; Pile Grade A (PGA); Radiolytic oxidation


Dive into the research topics of 'Graphite in Gas-Cooled Reactors'. Together they form a unique fingerprint.

Cite this