Ald coating of nuclear fuel actinides materials
US-2015063524-A1 · Mar 5, 2015 · US
US11145425B2 · US · B2
| Field | Value |
|---|---|
| Publication number | US-11145425-B2 |
| Application number | US-201916260889-A |
| Country | US |
| Kind code | B2 |
| Filing date | Jan 29, 2019 |
| Priority date | Jan 30, 2018 |
| Publication date | Oct 12, 2021 |
| Grant date | Oct 12, 2021 |
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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 U 3 Si 2 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 U 3 Si 2 , then the oxidation resistant particles can have a particle size distribution less than that of the UN or U 3 Si 2 .
Opening claim text (preview).
What is claimed is: 1. A method comprising: mixing a powdered fissile material selected from the group consisting of UN and U 3 Si 2 with an additive selected from oxidation resistant materials, the powdered fissile material comprising grains having grain boundaries; pressing the mixed fissile and the additive into a pellet; and, sintering the pellet to a temperature greater than the melting point of the additive sufficient for melting of the additive into the grain boundaries of the fissile material and densifying the pellet, wherein the additive has a melting point greater than the sintering temperature of the fissile material, and has a median particle size less than that of the UN or U 3 Si 2 . 2. The method recited in claim 1 wherein the powdered 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 method recited in claim 1 wherein the additive is present in amounts less than 20 weight percent of the fissile material. 4. The method recited in claim 1 wherein the sintering is selected from the group consisting of pressureless sintering, hot pressing, hot isostatic pressing, spark plasma sintering, field assisted sintering, and flash sintering. 5. The method 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 . 6. The method 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 . 7. The method recited in claim 1 wherein the vapor deposition is used to coat the outside of the unsintered pellet with the additive and to penetrate the additive into the pellet body of the UN or U 3 Si 2 . 8. The method 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 . 9. The method recited in claim 1 wherein the additive coats to the U 3 Si 2 or UN powders to form protective layers through vapor deposition before pressing into pellets and sintering. 10. The method recited in claim 9 wherein the vapor deposition is selected from the group consisting of physical vapor deposition, chemical vapor deposition, and atomic layer deposition. 11. A method comprising: mixing a powdered fissile material UN with an additive, the powdered fissile material comprising grains having grain boundaries; pressing the mixed fissile and the additive into a pellet; and sintering the pellet to a temperature greater than the melting point of the additive sufficient for melting of the additive into the grain boundaries of the fissile material and densifying the pellet, wherein the additive has a melting point lower than the sintering temperature of the fissile material, and the additive is a borosilicate glass. 12. A method comprising: mixing a powdered fissile material U 3 Si 2 with an additive, the powdered fissile material comprising grains having grain boundaries; pressing the mixed fissile material and the additive into a pellet; and sintering the pellet to a temperature greater than the melting point of the additive sufficient for melting of the additive into the grain boundaries of the fissile material and densifying the pellet, wherein the additive has a melting point lower than the sintering temperature of the fissile material, and the additive is a borosilicate glass.
by hydrostatic or thermo-pneumatic canning {in general by pressing without lengthening, e.g. explosive coating} · CPC title
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
Ceramic fuel · CPC title
by gas phase techniques · CPC title
characterised by the order of addition of constituents or additives · CPC title
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