[3G06-10] Molten Chloride Salt Reactor 1

11:40 AM - 11:55 AM JST(2:40 AM - 2:55 AM UTC)

[3G09] Feasibility Study of Integral Molten Chloride Salt Fast Reactor (IV)(4) Consideration of waste disposal methods

*Masahiko Nakase¹ (1. Tokyo Institute of Technology)

Keywords:

Chloride molten salt fast reactors,Waste disposal,Pyroprocessing,Cl-36,Cl-37,Dehalogenation,Minimization of repository area

The disposal methods for wastes from chloride molten salt fast reactors were analyzed through a literature survey. While various solidification materials have shown leachability and radiation resistance, there are no established disposal concepts, nuclide migration calculations, or safety analyses during disposal. In contrast, ³⁶Cl, a long half-life isotope, significantly impacts radiation doses in current aqueous reprocessing cycles. Its treatment varies based on whether it is directed to high-level or TRU waste, making it crucial to consider ³⁷Cl recovery and nuclear data in waste disposal strategies. Converting waste from molten salt to oxide form through dehalogenation can facilitate comparison with existing disposal methods and reduce repository area by improving waste content ratios. This presentation discusses considerations for disposing of waste from chloride molten salt fast reactors based on a literature review.