Nuclear fuel structure and method of making a nuclear fuel structure using a detachable cathode material
US-2016376723-A1 · Dec 29, 2016 · US
US9190179B2 · US · B2
| Field | Value |
|---|---|
| Publication number | US-9190179-B2 |
| Application number | US-201113275784-A |
| Country | US |
| Kind code | B2 |
| Filing date | Oct 18, 2011 |
| Priority date | Oct 20, 2010 |
| Publication date | Nov 17, 2015 |
| Grant date | Nov 17, 2015 |
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Provided are a method of controlling the compositional gradient and solubility of doped-additives at grain boundaries during sintering of a uranium-based oxide green pellet including the additives, and a method of manufacturing a sintered nuclear fuel pellet having a large grain size using the same. The grain boundary solubility of the doped-additives is maintained at a certain level by stepwise varying of an oxygen partial pressure during isothermal sintering of a uranium-based oxide green pellet including the additives. The method of manufacturing a sintered nuclear fuel pellet having a large grain size includes preparing additive mixed uranium oxide powder, forming an additive mixed uranium oxide green pellet using the mixed powder, heating the green pellet to a sintering temperature in a gas atmosphere having a low oxygen partial pressure, and sintering while a sintering gas atmosphere is changed to stepwise increase an oxygen partial pressure at the isothermal sintering temperature.
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The invention claimed is: 1. A method of manufacturing a sintered nuclear fuel pellet having a large grain size, the method comprising: mixing an additive powder and a uranium oxide powder to prepare an additive mixed uranium oxide powder; forming an additive mixed uranium oxide green pellet by using the mixed powder; heating the green pellet to an isothermal sintering temperature in an atmosphere control gas having an oxygen partial pressure corresponding to a minimum oxygen partial pressure of isothermal sintering or less; and changing a sintering gas atmosphere to perform the isothermal sintering such that an oxygen partial pressure is stepwise increased three times at the isothermal sintering temperature. 2. The method of claim 1 , wherein an amount of additive cations with respect to about 1 g of uranium-based cations in the uranium oxide green pellet is about 10-2000 μg. 3. The method of claim 1 , wherein the additive powder is a powder mixed with at least one or more of a chromium (Cr)-compound, an aluminum (Al)-compound, and a yttrium (Y)-compound. 4. The method of claim 3 , wherein the Cr-compound, the Al-compound, and the Y-compound are at least one or more selected from the group consisting of oxides, nitrates, stearates, chlorides, and hydroxides. 5. The method of claim 1 , wherein in the preparing of the additive mixed uranium oxide powder, a UO 2 -based powder is a UO 2 powder or a powder mixed with the UO 2 powder and one or more of a PuO 2 powder, a Gd 2 O 3 powder, and a ThO 2 powder. 6. The method of claim 1 , wherein the atmosphere control gas is a hydrogen gas or a mixing gas of a hydrogen gas and at least one or more gases selected from the group consisting of carbon dioxide, water vapor, and inert gases. 7. The method of claim 1 , wherein the forming of the green pellets is performed by a step of putting the additive mixed uranium oxide powder in a forming mold and molding at a pressure of about 3-5 tons/cm 2 . 8. The method of claim 1 , wherein the additive mixed uranium oxide powder comprises at least one or more of PuO 2 powder, Gd 2 O 3 powder, and ThO 2 powder.
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