This 5-day course is dedicated to topics covering neutron transport, fluid dynamics and heat transfer. It can be followed either in-person classes or fully online and aims at presenting the main algorithms in the computer codes used by the industry and in academia for the macroscopic modelling of nuclear systems. The underlying methods used in such codes – together with their assumptions and limitations-, will be thoroughly presented, so that codes could be used with confidence. During the course, attendees will also have to develop a one-dimensional coupled model of a heterogeneous sodium-cooled reactor using the presented methods.

LEARNING OBJECTIVES

Once completing the course, attendees should be able to:

• know the governing equations describing neutron transport, flow transport, and heat transfer in nuclear reactors
• know the modelling strategies used for neutron transport, flow transport, heat transfer in nuclear reactors, and for their coupling
• understand the limitations of the different modelling strategies

TARGET AUDIENCES

• MSc & PhD students having some background knowledge in nuclear engineering
• nuclear engineers
• reactor physicists
• nuclear safety analysts

The course is free of charge. Participants have nevertheless to cover their own expenses (travel, food, and accommodation).