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Neutronic Design Implications of Chlorine Isotopic Enrichment in Moderating-reflector Molten Salt Fast Reactors
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DOI：10.1016/j.net.2026.104556.png)
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Abstract
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This work investigates the neutronic implications of reduced 37Cl enrichment in a 200 MWth long-life molten salt fast reactor (MSFR) employing a moderating reflector such as BeO or MgO. This flux-trapped configuration reduces the required fissile inventory through local moderation while retaining the advantages of MSFRs. Although highly enriched 37Cl is preferred for neutron economy, especially with a moderating reflector, its cost may be comparable to that of high-assay low-enriched uranium (HALEU). Neutronic analyses were performed to assess the feasibility of reduced chlorine enrichment and the associated 35Cl-related physics. Spectrally dependent neutron absorption of 35Cl was evaluated for various chlorine enrichment levels, active core sizes, and reflector materials, while quantifying neutron leakage from the active core, the neutron energy spectrum, and the 35Cl capture spectrum. The impact of 35Cl on neutron multiplication factors was further evaluated together with major reaction rates, clarifying its influence on the fuel and reflector temperature coefficients through changes in the capture-to-fission ratio. In addition, a practical design employing 65 at.% 37Cl was developed for a 200 MWth MSFR, and core performance, neutronic properties, excess reactivity control, and corrosive product inventories were assessed. The Serpent 2 continuous-energy Monte Carlo code was used for neutronic calculations.
Keywords:
Molten salt fast reactor
Chloride salt
Moderating reflector
Chlorine enrichment
Small long-life reactor
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