GRAIN BOUNDARY ENHANCED UN AND U3Si2 PELLETS WITH IMPROVED OXIDATION RESISTANCE
US-2019237206-A1 · Aug 1, 2019 · US
US9299464B2 · US · B2
| Field | Value |
|---|---|
| Publication number | US-9299464-B2 |
| Application number | US-95911510-A |
| Country | US |
| Kind code | B2 |
| Filing date | Dec 2, 2010 |
| Priority date | Dec 2, 2010 |
| Publication date | Mar 29, 2016 |
| Grant date | Mar 29, 2016 |
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Various embodiments of a nuclear fuel for use in various types of nuclear reactors and/or waste disposal systems are disclosed. One exemplary embodiment of a nuclear fuel may include a fuel element having a plurality of tristructural-isotropic fuel particles embedded in a silicon carbide matrix. An exemplary method of manufacturing a nuclear fuel is also disclosed. The method may include providing a plurality of tristructural-isotropic fuel particles, mixing the plurality of tristructural-isotropic fuel particles with silicon carbide powder to form a precursor mixture, and compacting the precursor mixture at a predetermined pressure and temperature.
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What is claimed is: 1. A nuclear fuel comprising: a fuel element comprising a plurality of tristructural-isotropic fuel particles intermixed in a silicon carbide matrix, wherein the silicon carbide matrix separates at least one of the plurality of tristructural-isotropic fuel particles embedded in the silicon carbide matrix from the other tristructural-isotropic fuel particles embedded in the silicon carbide matrix, wherein the silicon carbide matrix has a density substantially equal to the theoretical density of stoichiometric silicon carbide. 2. The nuclear fuel of claim 1 , wherein each of the tristructural-isotropic fuel particles comprises a fuel kernel disposed substantially at the center and a ceramic layer surrounding the fuel kernel. 3. The nuclear fuel of claim 1 , wherein the fuel element has a shape of a cylindrical pellet. 4. The nuclear fuel of claim 1 , further comprising: a tubular enclosure defining an interior space, wherein an outer surface of the tubular enclosure is configured to contact a coolant of a nuclear reactor, wherein the fuel element is disposed in the interior space. 5. The nuclear fuel of claim 4 , wherein the tubular enclosure is a metallic cladding tube. 6. The nuclear fuel of claim 1 , further comprising a graphite block having one or more holes, wherein the fuel element is disposed inside the one or more holes. 7. The nuclear fuel of claim 1 , wherein the plurality of tristructural-isotropic fuel particles comprise transuranic elements extracted from a spent fuel of a light water reactor. 8. The nuclear fuel of claim 1 , wherein the plurality of tristructural-isotropic fuel particles comprise transuranic elements extracted from a nuclear weapon. 9. A nuclear fuel comprising: a fuel element comprising a plurality of tristructural-isotropic fuel particles intermixed in a silicon carbide matrix, wherein the silicon carbide matrix separates at least one of the plurality of tristructural-isotropic fuel particles embedded in the silicon carbide matrix from the other tristructural-isotropic fuel particles embedded in the silicon carbide matrix, wherein the silicon carbide matrix is near-stoichiometric and has pockets of porosity of not more than 4%, and wherein the pockets include only rare earth oxides or tramp elements. 10. The nuclear fuel of claim 9 , wherein the fuel element has a shape of a cylindrical pellet. 11. The nuclear fuel of claim 9 , further comprising: a tubular enclosure defining an interior space, wherein an outer surface of the tubular enclosure is configured to contact a coolant of a nuclear reactor, wherein the fuel element is disposed in the interior space. 12. The nuclear fuel of claim 9 , further comprising a graphite block having one or more holes, wherein the fuel element is disposed inside the one or more holes. 13. The nuclear fuel of claim 9 , wherein the plurality of tristructural-isotropic fuel particles comprise transuranic elements extracted from a spent fuel of a light water reactor. 14. The nuclear fuel of claim 9 , wherein the plurality of tristructural-isotropic fuel particles comprise transuranic elements extracted from a nuclear weapon.
Ceramic fuel · CPC title
Manufacture of fuel elements or breeder elements contained in non-active casings · CPC title
Coated fuel particles · CPC title
by vibrational compaction or tamping {of fuel in the jacket} · 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
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