Apparatus and Method for Stripping Tritium from Molten Salt

摘要

A method of stripping tritium from flowing stream of molten salt includes providing a tritium-separating membrane structure having a porous support, a nanoporous structural metal-ion diffusion barrier layer, and a gas-tight, nonporous palladium-bearing separative layer, directing the flowing stream of molten salt into contact with the palladium-bearing layer so that tritium contained within the molten salt is transported through the tritium-separating membrane structure, and contacting a sweep gas with the porous support for collecting the tritium.

主权项

1. In a nuclear reactor system including a nuclear reactor, a utilization means for utilizing heat energy generated by the nuclear reactor, and a flowing stream of molten salt for transferring the heat energy from the nuclear reactor to the utilization means, wherein the improvement comprises:
a. a tritium-separating membrane structure having a porous support, a nanoporous structural metal-ion diffusion barrier layer supported by and in contact with said porous support, and a gas-tight, nonporous palladium-bearing separative layer supported by and in contact with said nanoporous structural metal-ion diffusion barrier layer; b. means for directing the flowing stream of molten salt into contact with said palladium-bearing layer so that tritium contained within the molten salt is transported through said tritium-separating membrane structure; and c. means for contacting a sweep gas with said porous support for collecting the transported tritium.