High efficiency continuous-flow production of radioisotopes
US-2017337998-A1 · Nov 23, 2017 · US
US9564251B2 · US · B2
| Field | Value |
|---|---|
| Publication number | US-9564251-B2 |
| Application number | US-201414333627-A |
| Country | US |
| Kind code | B2 |
| Filing date | Jul 17, 2014 |
| Priority date | Jul 17, 2014 |
| Publication date | Feb 7, 2017 |
| Grant date | Feb 7, 2017 |
A practical reading order for non-experts. Skip the full description unless you need deep technical detail.
What the patent document calls the invention.
A short plain-language summary of the technical disclosure.
Who owns or filed the patent and who is credited as inventor.
Filing, priority, publication, and grant dates set the timeline.
The legal scope of protection — read this for what is actually claimed.
Technology tags used to group this patent with similar filings.
Prior art links and similar publications in this corpus.
Official abstract text for this publication.
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.
Opening claim text (preview).
What is claimed is: 1. 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 selected from a group consisting of stainless steel and nickel-based alloy, 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 absorbed by said nonporous palladium-bearing separative layer, transported through said tritium-separating membrane structure; and c. contacting a sweep gas with said porous support for collecting the tritium. 2. A method in accordance with claim 1 wherein said porous support comprises 316 stainless steel. 3. A method 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 method in accordance with claim 1 wherein said gas-tight, nonporous palladium-bearing separative layer comprises a palladium alloy. 5. A method in accordance with claim 4 wherein said palladium alloy comprises a palladium-silver alloy. 6. A method in accordance with claim 1 wherein said tritium-separating membrane structure comprises at least one structure disposed within an outer containment structure.
Other isotopes not provided for in the groups listed above · CPC title
Recovery of specific isotopes from irradiated targets · CPC title
Processing (separating different isotopes of the same chemical element B01D59/00) · CPC title
specially adapted for liquids (decontamination of liquids G21F9/04) · CPC title
Fused salt, oxide or hydroxide compositions · CPC title
Related publications grouped by family.
Answers are generated from the same data shown on this page.