Fluoride salt-cooled high-temperature reactors (FHRs), cooled with liquid (molten) salt, fuelled with TRISO-based fuel are a potential molten salt reactor (MSR) design.
Such reactor designs share certain similarities (heat removal by molten salt) with the historic molten salt reactor experiment (MSRE), but also present a fundamental difference in having solid fuel, either in the form of circulating pebbles or in hexagonal fuel elements. The complex fuel geometry and novel materials challenge existing simulation tools. At the same time, there are no experimentally-obtained results making cross-verification using different reactor physics codes and methods a suitable approach to verify performance and identify gaps in simulation capability.
The purpose of this benchmark is to:
The benchmark proposal was accepted at the 2019 Expert Group on Reactor Physics and Advanced Nuclear Systems (EGRPANS) meeting.
Ian Hill, NEA
Bojan Petrovic, Co-ordinator, Georgia Institute of Technology:
Under the guidance of the Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems (WPRS), the Expert Group on Physics of Reactor Systems (EGPRS) performs specific tasks associated with reactor physics aspects of present and future nuclear power systems.
The Subgroup on Uncertainty Analysis in Modelling (UAM) for Design, Operation and Safety Analysis of Sodium-cooled Fast Reactors (SFR-UAM) was formed to check the use of best-estimate codes and data.
The Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems (WPRS) studies the reactor physics, fuel performance, and radiation transport and shielding in present and future nuclear power systems.