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

This study presents a computational methodology for analyzing isotopic evolution and associated uncertainties in molten salt reactors (MSRs), focusing on both fluoride- and chloride-based fuel salts. The primary goal is to enhance the understanding of isotopic behavior in MSRs and provide data to support future experimental efforts. The methodology integrates transport-coupled depletion calculations using OpenMC, equilibrium thermodynamics modeling with Thermochimica, and a corrosion model. Sensitivity analyses are performed to evaluate the impact of power density, air ingress, and humidity content on isotopic evolution in MSR concepts. This study examines representative F- and Cl-based MSR designs, highlighting the dominant influence of power density on isotopic composition, which significantly affects isotope production and depletion rates, accounting for approximately 76% of the observed variance in element concentration. Air ingress and humidity content also affect the redox potential, solubility of heavier elements, and corrosion rates, thereby altering the expected isotopic evolution in the reactor. On average, air ingress accounts for around 17% of the variance in element concentrations, while humidity explains the remaining 7%. These variances differ significantly from element to element, depending on the element’s role in depletion, redox potential evolution, and galvanic corrosion. The findings indicate that power density, air ingress, and humidity content are all critical factors for optimizing reactor design and operational strategies. Furthermore, the study provides expected ranges for key impurities in the fuel salt, which are crucial for guiding future experimental studies and refining MSR designs. Finally, this study demonstrates the importance of modeling depletion coupled with the evolution of redox potential and chemical interactions in MSR fuel salts.. Authors: Tano, Mauricio E. [Idaho National Laboratory (INL), Idaho Falls, ID (United States)] (ORCID:0000000334173869); Walker, Samuel A. [Idaho National Laboratory (INL), Idaho Falls, ID (United States)]; Abou-Jaoude, Abdalla [Idaho National Laboratory (INL), Idaho Falls, ID (United States)]; Roper, Robin [Idaho National Laboratory (INL), Idaho Falls, ID (United States)]; Karlsson, Toni [Idaho National Laboratory (INL), Idaho Falls, ID (United States)]. DOE Contract: AC07-05ID14517. Subjects: 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; Characterization; Corrosion; Depletion; MSR; Operation