The core of the advanced gas-cooled reactor (AGR) is constructed with a large number of nuclear graphite components. These components form channels for fuel and control rods and also restrain the core by acting as a keying system. The structural integrity of these components is of prime importance for a safe operation of the AGR. Fuel channels are built up of cylindrical bricks, which are exposed to fast neutron irradiation and radiolytic oxidation during the life of a reactor. As a result, the bricks experience highly nonlinear deformation and material property changes, which generate a complex stress state within each fuel brick and its interacting graphite components.

The behaviour and assessment of graphite components is generally conducted using time-integrated finite element (FE) modelling. The deformation and material properties used in this type of assessment are calculated as a function of fast neutron irradiation, irradiation temperature and weight loss, to reflect radiation aging of nuclear graphite over the reactor’s life.

In this webinar, Dr Muhammad Fahad, a Senior Engineer at Engineering Analysis Services Limited (EASL), will demonstrate how COMSOL Multiphysics^® is used to address a complex issue related to AGR fuel bricks. The webinar will focus on the modelling complexity, which will include issues encountered during model development and how these were addressed.

Disclaimer: The work presented here is funded by the EDF Energy UK. The contents, including any opinions and/or conclusions expressed, are those of the presenter alone and do not necessarily reflect EDF Energy UK policy.

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