Container Materials for Molten Salt Nuclear Reactors: Problems and Research

In view of the increased interest in a molten salt reactor (MSR), the problem of choosing container materials compatible with molten fluoride salts containing a fuel additive and fission products at temperatures up to 750°C is considered. The results of corrosion tests of promising high-nickel alloys with a fuel salt and an intermediate coolant of MSR, including experimental results at the National Research Center Kurchatov Institute are presented.