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DOE OSTI · 1649079

MSR Fuel Salt Qualification Methodology

Holcomb, David Eugene·Poore III, Willis P.·Flanagan, George F.
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Abstract

This report documents the continuing activities at Oak Ridge National Laboratory (ORNL) in support of the US Nuclear Regulatory Commission (NRC) efforts to develop an efficient, appropriate process for liquid fuel salt system qualification. Fuel qualification for salt-cooled molten salt reactors (MSRs) is part of the ongoing coated particle fuel qualification effort. Fuel qualification is a process which provides high confidence that physical and chemical behavior of fuel is sufficiently understood so that it can be adequately modeled for both normal and accident conditions, reflecting the role of the fuel design in the overall safety of the facility. Uncertainties are defined so that calculated fission product releases include the appropriate margins to ensure conservative calculation of radiological dose consequences. The initial phase of ORNL’s activities is documented in ORNL/LTR-2018/1045 Molten Salt Reactor Fuel Qualification Considerations and Challenges.

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Holcomb, David Eugene, Poore III, Willis P., Flanagan, George F.. 2020-07-01. MSR Fuel Salt Qualification Methodology. https://doi.org/10.2172/1649079

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