Apparatus and Method for Stripping Tritium from Molten Salt

Patent metadata

Field	Value
Publication number	US-2016019993-A1
Application number	US-201414333627-A
Country	US
Kind code	A1
Filing date	Jul 17, 2014
Priority date	Jul 17, 2014
Publication date	Jan 21, 2016
Grant date	—

Abstract

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.

First claim

What is claimed is:

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.

2 . A nuclear reactor system in accordance with claim 1 wherein said porous support comprises a material selected from the group consisting of 316 stainless steel and a nickel-based alloy.

3 . A nuclear reactor system 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 . A nuclear reactor system in accordance with claim 1 wherein said gas-tight, nonporous palladium-bearing separative layer comprises a palladium alloy.

5 . A nuclear reactor system in accordance with claim 4 wherein said palladium alloy comprises a palladium-silver alloy.

6 . A nuclear reactor system in accordance with claim 1 wherein said tritium-separating membrane structure comprises at least one structure disposed within an outer containment structure.

7 . A method of stripping tritium from flowing stream of molten salt comprising the steps of:
a. providing 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. 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. contacting a sweep gas with said porous support for collecting the tritium.

8 . A method in accordance with claim 7 wherein said porous support comprises a material selected from the group consisting of 316 stainless steel and a nickel-based alloy.

9 . A method in accordance with claim 7 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.

10 . A method in accordance with claim 7 wherein said gas-tight, nonporous palladium-bearing separative layer comprises a palladium alloy.

11 . A method in accordance with claim 10 wherein said palladium alloy comprises a palladium-silver alloy.

12 . A method in accordance with claim 7 wherein said tritium-separating membrane structure comprises at least one structure disposed within an outer containment structure.

Assignees

• Ut Battelle Llc

Inventors

• Holcomb David E
• Wilson Dane F

Classifications

• G21F9/308

  by melting the waste (G21F9/305, G21F9/32 take precedence) · CPC title

• G21G2001/0094

  Other isotopes not provided for in the groups listed above · CPC title

• G21G1/001 Primary

  Recovery of specific isotopes from irradiated targets · CPC title

• G21F9/06

  Processing (separating different isotopes of the same chemical element B01D59/00) · CPC title

• G21C3/54

  Fused salt, oxide or hydroxide compositions · CPC title