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Abstract
British Energy Ltd (BE) operates all seven twin advanced gas-cooled reactor (AGR) power stations in the UK. In the AGRs, neutrons from the heat-producing process of fuel fission are moderated by graphite, and both graphite and fuel are cooled by pressurised carbon dioxide. The moderation process, together with corrosion by the coolant, alters the material properties of the graphite, which in turn influences the functionality of the moderator core. As a consequence, it is important to BE to understand the behaviour of irradiated graphite. This paper explains that a materials model of how graphite materials properties evolve with increasing dose and fluctuating temperature was developed.
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