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

Seminarium Zakładu Energetyki Jądrowej i Analiz Środowiska
Prelegent i afiliacja: 
Maciej Skrzypek
wt., 2023-02-28 11:30 do 12:30

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.

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