Professor Barry Marsden will discuss the irradiation behaviour of nuclear graphite. Coffee will be available from 19:00, and the talk will begin 19:30.
Graphite is an excellent, but not perfect, moderator material. It was the chosen moderator for the first Piles in Chicago, was used by the USA, Russia, France and the UK in the reactors built for the production of plutonium. Nuclear graphite was the moderator of choice in the early power producing Magnox, UNGG and Russian LWGMR and is the main moderator in the AGRs and RBMK reactors which will still be operating into the next decade. In addition to this the next Generation IV very high temperature reactors VHTR will employ graphite in reactor designs aimed at gas outlet temperatures of 1000oC.
In reactor, during operation, the properties and dimensions of nuclear graphite components are significantly changed leading to component distortion and the generation on internal stresses. It is therefore important that these changes are taken into account in the design and operation of the graphite moderated reactors.
This talk will cover the nuclear manufacture and the influence this has on irradiation behaviour and how that reflects on reactor operation. The talk will reflect the significant amount of research which has gone into, and is still being devoted, to understanding the irradiation behaviour of nuclear graphite.
Coffee will be available from 19:00, and the talk will begin at 19:30.