Safety assessment of High Temperature Gas-cooled Reactor using parametric code

Nuclear reactors are probably one of the best solutions to solve the world's energy problems and are emerging as a safe and clean source of energy in the public consciousness. On the one hand side, they can provide sustainable and zero-emission energy, on the other hand, the licensing process and construction take a lot of time. Before the implementation of any type of nuclear facility, a complex and time-consuming safety assessment is required, which can prove that the concept is safe. The process needs to be made using a number of numerical methods for each specific field of interest (thermal-hydraulics, neutronics, fuel behaviour, structural mechanics or environmental studies).

In this presentation, the thermal-hydraulic aspects required in the Preliminary Safety Report will be described from the perspective of parametric code usage on the example of High Temperature Gas-cooled Reactor.