Functionally graded lattice cermet fuel structure with shape corresponding to a mathematically-based periodic solid, particularly for nuclear thermal propulsion applications
US-12159726-B2 · Dec 3, 2024 · US
US10043595B2 · US · B2
| Field | Value |
|---|---|
| Publication number | US-10043595-B2 |
| Application number | US-201314060432-A |
| Country | US |
| Kind code | B2 |
| Filing date | Oct 22, 2013 |
| Priority date | Dec 31, 2012 |
| Publication date | Aug 7, 2018 |
| Grant date | Aug 7, 2018 |
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A uranium dioxide nuclear fuel pellet has about 50 to about 400 μM (with respect to a 3-dimentional size) microcells formed of a ceramic material having a chemical attraction with fission products generated in the nuclear fuel pellet to absorb and trap the fission products, such that the extraction of the fission product may be retrained in a normal operation condition and that the performance of the nuclear fuel may be enhanced by mitigating PCI. In addition, highly radioactive fission products including Cs and I having a large generation amount or a long half-life enough to affect the environments can be trapped in the pellet in an accident condition, without being released outside.
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What is claimed is: 1. A uranium dioxide nuclear fuel pellet comprising: uranium dioxide grains; and micro-partitions partitioning and contacting the uranium dioxide grains, wherein the micro-partitions consist essentially of a ceramic material that melts in a temperature range of 1200-1800° C., wherein the ceramic material is a mixture comprising two or more selected from the group consisting of Si-compounds, Ti-compounds, Al-compounds, Mg-compounds, and Mn-compounds, and wherein the mixture further comprises the Ti-compounds in an amount of at least 37.08 wt % or the Mn-compounds in an amount of 14.0 wt %. 2. The uranium dioxide nuclear fuel pellet of claim 1 , further comprising: metallic particles dispersed in the uranium dioxide grains and configured to react with oxygen more easily than uranium dioxide does. 3. The uranium dioxide nuclear fuel pellet according to claim 2 , wherein the metallic particles comprise Cr or Mo. 4. The uranium dioxide nuclear fuel pellet according to claim 2 , wherein an average size of the metallic particles is about 0.3 μm to about 10 μm. 5. The uranium dioxide nuclear fuel pellet according to claim 1 , wherein the micro-partitions define a plurality of microcells, wherein each of at least some of the microcells contains a single grain of uranium oxide. 6. The uranium dioxide nuclear fuel pellet according to claim 1 , wherein one of the micro-partitions is located between two immediately neighboring grains of the uranium dioxide grains and contacts the two immediately neighboring grains.
Manufacture of fuel elements or breeder elements contained in non-active casings · CPC title
Fuel elements with porous or capillary structure · CPC title
Means for storage or immobilisation of gases in fuel elements · CPC title
Details of the construction within the casing · CPC title
Ceramic fuel · CPC title
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