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.Note that COMSOL will follow up with all registrants about this event and any related questions.