Nuclear thermalhydraulics

Flows in nuclear reactors are, like in steel-making, hard to measure experimentally so justify the use of detailed CFD modelling. 

Corium flow and heat transfer in CANDU reactors under severe accident conditions

The worst case station black-out power accident could result an inability to remove sufficient decay het from the reactor core. The core would then overheat, dry-out then collapse of the core to the bottom of the dried-out calandria vessel. The subsequent melting of the core material would form a corium pool, and its containment within the calandria depends on the heat flow and the convective circulation flow patterns in the liquid corium.  Modelling the corium melt and flow and heat transfer is being undertaken to investigate core containment under such accident conditions. .

Modelling molten salt flow and heat transfer in Small Modular Reactors

more to come

Unsteadiness in axial channel flows

Fundamental modelling and understanding of these flows which occur between the fuel rods in CANDU and PWR reactors. 

Cross-section of velocity and temperature in a LES of a fully molten corium pool (top and middle); temperature and solidification interfaces in URANS later in time (bottom).