Evaluation of mitigation strategies for radioactive fission gases in fluoride-salt-cooled high-temperature reactors

Progress on Near-Term Tasks for the Development of Advanced Reactor Mechanistic Source Term Modeling and Simulation Tools

“…The implementation of tritium transport phenomena in system-level transient safety analysis codes such as SAM is necessary to understand how reactor behavior may influence tritium releases. Similarly, other 1D system-level thermal fluids codes have been enhanced to accommodate tritium transport phenomena in FHRs such as a recent modeling effort comparing heat exchanger designs and capture materials to investigate reducing tritium leakage rates [73].…”