LSM Seminars

Towards Simulation of Molten Salt Reactor Dynamics Using the FAST Code System

by Dr Dorde Petrovic

Europe/Zurich
OHSA/E13

OHSA/E13

Description

Abstract:
The FAST code system is an advanced, coupled computational tool developed at the Advanced Nuclear System group to perform neutronic, thermal-hydraulic, and fuel analysis for the static and transient behavior of advanced fast-spectrum reactor systems, including a wide range of employed coolants and fuels. Over the years, the FAST code system has been adapted for the simulation of Molten Salt Reactor (MSR) technology as well, which required a great deal of modification to the codes that constitute it (namely TRACE and PARCS).

oday, the code system represents a powerful tool for the simulation of transient behavior and accidental sequences in MSRs and, as such, holds the potential to play an important role in the design and safety studies of this technology.

his talk will introduce the audience to the main components of the FAST code system, the modifications introduced to enable it to simulate MSR-specific phenomena, and the validation performed against available historical experimental data. Ultimately, the most common MSR core designs (a channel-wise system characterized by a thermalized spectrum and an open-space system characterized by a fast spectrum) will be exposed to a series of accident initiators, and the physics governing their dynamic behavior will be presented and extensively discussed.

Bio:
Đorđe earned his Master’s degree in Nuclear Engineering from the Swiss Federal Institute of Technology in Zürich (ETH Zürich) and his PhD degree in Nuclear Engineering Science from University of Leuven (KU Leuven) in Belgium. Throughout his academic journey, he has been closely affiliated with the Paul Scherrer Institute (PSI) and the Belgian Nuclear Research Centre (SCK CEN), where his research focused on reactor physics and the safety analysis of advanced fast-spectrum reactor technologies cooled by liquid metals. Following a (brief) postdoctoral appointment in the Advanced Nuclear Systems group at PSI, Đorđe will rejoin SCK CEN in early October to lead the Criticality Safety programme for their new Lead-cooled Fast Reactor design.

 

Organised by

The Laboratory for Simulation and Modeling

Dr. Jan Kren