Steady-state radiochemical transport model of the molten salt reactor experiment

Shahbazi, Shayan; Romano, Paul K.; Fei, Tingzhou; Grabaskas, David

doi:10.1007/s10967-022-08535-3

Cited by 5 publications

(2 citation statements)

References 23 publications

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“…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). Lastly, radionuclide species transport in the MSRE was conducted albeit without coupling depletion and thermochemistry in the analysis (Shahbazi et al, 2022b).…”

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%

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

et al. 2023

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“…As mentioned, a custom radiochemical transport model of MSRs was created to support fission product behavior analyses and has been demonstrated on the primary loop of the MSRE [78]. The model accounts for radiochemical transport as a function of generation in the core and from precursor decay, advective flow through a loop, losses due to chemical removal defined by a constant rate, and losses due to decay.…”

Section: Msr Radiochemical Transport Modelmentioning

confidence: 99%

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

Shahbazi,

Kam,

Starkus

et al. 2022

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Coupled neutronics, thermochemistry, corrosion modeling and sensitivity analyses for isotopic evolution in molten salt reactors

Tano,

Walker,

Abou-Jaoude

et al. 2025

Progress in Nuclear Energy

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Steady-state radiochemical transport model of the molten salt reactor experiment

Cited by 5 publications

References 23 publications

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

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

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

Coupled neutronics, thermochemistry, corrosion modeling and sensitivity analyses for isotopic evolution in molten salt reactors

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