Grain boundary enhanced UN and U3Si2 pellets with improved oxidation resistance

US11551822B2 · US · B2

Patent metadata
FieldValue
Publication numberUS-11551822-B2
Application numberUS-202117473433-A
CountryUS
Kind codeB2
Filing dateSep 13, 2021
Priority dateJan 30, 2018
Publication dateJan 10, 2023
Grant dateJan 10, 2023

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  1. Title

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  2. Abstract

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  3. Assignees and inventors

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  4. Key dates

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  5. First independent claim

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Abstract

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A method of forming a water resistant boundary on a fissile material for use in a water cooled nuclear reactor is described. The method comprises mixing a powdered fissile material selected from the group consisting of UN and U3Si2 with an additive selected from oxidation resistant materials having a melting or softening point lower than the sintering temperature of the fissile material, pressing the mixed fissile and additive materials into a pellet, sintering the pellet to a temperature greater than the melting point of the additive. Alternatively, if the melting point of the oxidation resistant particles is greater than the sintering temperature of UN or U3Si2, then the oxidation resistant particles can have a particle size distribution less than that of the UN or U3Si2.

First claim

Opening claim text (preview).

What is claimed is: 1. A nuclear fuel comprising: a pellet comprised of compressed and densified grains of a fissile material selected from the group consisting of UN and U 3 Si 2 , the grains having grain boundaries; and an oxidation resistant additive coating at least a portion of the grain boundaries of the fissile material; wherein the additive has a melting point greater than the sintering temperature of the fissile material, the additive is melted into at least a portion of the grain boundaries, and the additive has a median particle size less than that of UN or U 3 Si 2 . 2. The nuclear fuel recited in claim 1 wherein the fissile material is UN, and the additive is selected from the group consisting of tungsten and alloys containing at least 50 atomic % thereof, and UO 2 . 3. The nuclear fuel recited in claim 1 wherein the additive is present in amounts less than 20 weight percent of the fissile material. 4. The nuclear fuel recited in claim 1 wherein the median particle size of the additive is less than 10% of the median particle size of the UN or U 3 Si 2 . 5. The nuclear fuel recited in claim 1 wherein the median particle size of the additive is less than 1% of the median particle size of the UN or U 3 Si 2 . 6. The nuclear fuel recited in claim 1 wherein the powdered fissile material is U 3 Si 2 , and the additive is selected from the group consisting of molybdenum, titanium, chromium, thorium, tungsten, niobium, and zirconium, alloys containing at least 50 atomic % thereof, BeO, and UO 2 . 7. A nuclear fuel comprising: a pellet comprised of compressed and densified grains of a fissile material UN, the grains having grain boundaries; and an oxidation resistant additive coating at least a portion of the grain boundaries of the fissile material; wherein the additive has a melting point lower than the sintering temperature of the fissile material, the additive is melted into at least a portion of the grain boundaries, and the additive is a borosilicate glass. 8. The nuclear fuel recited in claim 7 wherein the additive is present in amounts less than 20 weight percent of the fissile material. 9. A nuclear fuel comprising: a pellet comprised of compressed and densified grains of a fissile material U 3 Si 2 , the grains having grain boundaries; and an oxidation resistant additive coating at least a portion of the grain boundaries of the fissile material; wherein the additive has a melting point lower than the sintering temperature of the fissile material, the additive is melted into at least a portion of the grain boundaries, and the additive is a borosilicate glass. 10. The nuclear fuel recited in claim 9 wherein the additive is present in amounts less than 20 weight percent of the fissile material.

Assignees

Inventors

Classifications

  • with coating on fuel or on inside of casing; with non-active interlayer between casing and active material {with multiple casings or multiple active layers} · CPC title

  • Refractory metals · CPC title

  • Gas infiltration of green bodies or pre-forms · CPC title

  • Metallic constituents or additives not added as binding phase · CPC title

  • Intergranular or grain boundary phases · CPC title

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What does patent US11551822B2 cover?
A method of forming a water resistant boundary on a fissile material for use in a water cooled nuclear reactor is described. The method comprises mixing a powdered fissile material selected from the group consisting of UN and U3Si2 with an additive selected from oxidation resistant materials having a melting or softening point lower than the sintering temperature of the fissile material, pressi…
Who is the assignee on this patent?
Westinghouse Electric Co Llc
What technology area does this patent fall under?
Primary CPC classification G21C3/623. Mapped technology areas include Physics.
When was this patent published?
Publication date Tue Jan 10 2023 00:00:00 GMT+0000 (Coordinated Universal Time) (B2). Legal status and post-grant events are not shown on this page.
What related patents are in patentsdb?
We list 2 related publications on this page (citations in our corpus or others sharing the same primary CPC).