Survey of Relevant Data from the MSRP to Guide Development of MSR Chemistry Modeling Benchmarks

Shahbazi, Shayan; Tano, Mauricio; Walker, Samuel; Tonks, Michael; Fang, Jun

doi:10.2172/1962308

Cited by 1 publication

(1 citation statement)

References 61 publications

(129 reference statements)

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“…Even more recently, the issue of depletion driven thermochemistry or chemistry-integrated fuel evolution was highlighted by the U.S. DOE's Advanced Reactor Technology-Molten Salt Reactor Program (MSRP) (Shahbazi, 2022a). An excellent and thorough review of thermochemical modeling for radionuclide speciation in molten salts was completed and is highlighted here by the authors for the inquisitive reader (Shahbazi et al, 2021).…”

Section: Literature Review Of Similar Workmentioning

confidence: 99%

Depletion-driven thermochemistry of molten salt reactors: review, method, and analysis

et al. 2023

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Molten salt reactors (MSRs) are innovative advanced nuclear reactors that utilize nuclear fuel by dissolving it in a high-temperature liquid salt. This unique feature differentiates MSRs from other types of reactors and allows for enhanced safety and economic performance. The liquid fuel also entails several multiphysics effects that can complicate reactor design and operation. One primary effect termed here as depletion-driven thermochemistry is a driving force in altering the multiphysics behavior of the reactor. Essentially, depletion-driven thermochemistry is the effect that fuel depletion has on changing the chemical redox potential of the fuel salt over time. As the fuel is consumed, the redox potential shifts toward a more oxidizing state. Without active control, the changing chemistry due to depletion increases corrosion thereby limiting reactor component lifetimes. Additionally, the changing redox potential of the fuel salt alters the vapor pressures of chemical species dissolved in the fuel salt. Changing vapor pressures of species in the fuel salt is an important parameter to understand when off-gassing volatile species during normal reactor operation, and for source term characterization during accident scenario transients. The present work represents a fundamental step toward modeling and coupling the driving physics (i.e., neutronics and chemistry) involved in altering the redox potential in an MSR. Here, the neutronic code Griffin models the depletion of the fuel-salt system, while the chemical equilibrium code Thermochimica calculates the thermochemical state of the isotopic inventory, using the Molten Salt Thermodynamic Database - Thermochemical (MSTDB-TC). These two codes are tightly coupled to predict the impact of fuel depletion in altering the chemistry in MSR systems. Redox potential control methods are discussed and can be modeled using this multiphysics approach. The vapor pressures of chemical species that could be extracted to an off-gas system, as determined by the reactor’s thermochemical state, are examined. The neutronics-chemistry coupling developed in this work is expected to have potential application for analyzing corrosion, source term evolution, and material safeguards in MSR systems. Lastly, suggestions for areas of further improvements of the models to expand these capabilities by incorporating other coupled physics effects is provided.

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Section: Literature Review Of Similar Workmentioning

confidence: 99%