Patent Number: 
Section: claims

1. A tritium-stripping apparatus 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, the tritium-stripping apparatus comprising:an outer containment structure;a tritium-separating membrane structure within the outer containment structure, the tritium-separating membrane structure including:a porous support selected from a group consisting of stainless steel and nickel-based alloy, and defining a first surface of the tritium-separating membrane structure;a nanoporous structural metal-ion diffusion barrier layer supported by and in contact with the porous support; anda gas-tight nonporous palladium-bearing separative layer supported by and in contact with the nanoporous structural metal-ion diffusion barrier layer, and defining a second surface of the tritium-separating membrane structure; anda sweep gas circulating between the outer containment structure and the first surface of the tritium-separating membrane structure;wherein the tritium-separating membrane structure is configured to receive the flowing stream of molten salt in contact with the gas-tight nonporous palladium-bearing separative layer so that tritium contained within the molten salt is absorbed by the gas-tight nonporous palladium-bearing separative layer and transported through the first surface and wherein the sweep gas circulates in contact with the porous support for collecting the transported tritium, and wherein the tritium-separating membrane structure is tubular and the first surface of the tritium-separating membrane structure is an outer surface of the tube and the second surface of the tritium-separating membrane structure is an inner surface of the tube. 2. The tritium-stripping apparatus in accordance with claim 1 wherein said porous support comprises 316 stainless steel. 3. The tritium-stripping apparatus in accordance with claim 1 wherein said structural metal-ion diffusion barrier layer comprises at least one material selected from the group consisting of yttrium-stabilized zirconia, scandia-stabilized zirconia, alumina, titania, chromia, and chromium nitride. 4. The tritium-stripping apparatus in accordance with claim 1 wherein said gas-tight nonporous palladium-bearing separative layer comprises a palladium alloy. 5. The tritium-stripping apparatus in accordance with claim 4 wherein said palladium alloy comprises a palladium-silver alloy. 6. The tritium-stripping apparatus in accordance with claim 1 wherein the outer containment structure is a tubular containment structure, wherein the sweep gas circulates between the tubular containment structure and the outer surface of the tubular tritium-separating membrane structure. 7. The tritium-stripping apparatus in accordance with claim 6 wherein the tubular tritium-stripping membrane structure is one of a plurality of tubular tritium-separating membrane structures within the tubular containment structure. 8. The tritium-stripping apparatus in accordance with claim 1 wherein the tritium-stripping system comprises a plurality of tubular tritium-separating membrane structures within the outer containment structure. 9. The tritium-stripping apparatus in accordance with claim 8 wherein the plurality of tritium-separating tubular membrane structures are U-shaped, and wherein the sweep gas circulates around the outer surface of the U-shaped tubular tritium-separating membrane.