Performing accurate numerical simulations of molten salt reactors is challenging, especially in case of fastspectrum designs, due to the unique physics phenomena characterizing these systems. The limitations of codes traditionally used in the nuclear community often require the development of novel high-fidelity multiphysics tools to advance the design of these innovative reactors. | Progress in Nuclear Energy 127 2020 103427 Contents lists available at ScienceDirect Progress in Nuclear Energy journal homepage http locate pnucene A multi-physics solver for liquid-fueled fast systems based on the discontinuous Galerkin FEM discretization Marco Tiberga Danny Lathouwers Jan Leen Kloosterman Delft University of Technology Department of Radiation Science and Technology Mekelweg 15 2629 JB Delft the Netherlands A R T I C L E I N F O A B S T R A C T Keywords Performing accurate numerical simulations of molten salt reactors is challenging especially in case of fast- Multi-physics modeling spectrum designs due to the unique physics phenomena characterizing these systems. The limitations of Coupling scheme codes traditionally used in the nuclear community often require the development of novel high-fidelity multi- Molten salt fast nuclear reactors physics tools to advance the design of these innovative reactors. In this work we present the most recent code Discontinuous Galerkin FEM SN transport developed at Delft University of Technology for multi-physics simulations of liquid-fueled fast reactors. The Incompressible RANS coupling is realized between an incompressible RANS model and an SN neutron transport solver. The models are implemented in two in-house codes based on the discontinuous Galerkin Finite Element discretization which guarantees high-quality of the solution. We report and discuss the results of preliminary simulations of the Molten Salt Fast Reactor at steady-state and during a Total Loss of Power transient. Results prove our code has capabilities for steady-state and transient analysis of non-moderated liquid-fueled reactors. 1. Introduction Some efforts have been made to equip classical codes used in the nuclear community to model traditional solid-fueled reactors with the Interest in molten salt reactors MSR has increased over the past two features necessary to address MSR simulations . Zanetti et al. decades .
