Low temperature chemical processing of graphite-clad nuclear fuels
US9793019B1 · kind B1 · utility
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14References
19Claims
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Key dates
| Filing date | Mar 26, 2014 |
| Grant date | Oct 17, 2017 |
| Priority date | — |
| Expiry date | Aug 18, 2036 |
Classification
- Technology area (CPC Y)Emerging Cross-Sectional Technologies
- CPC primaryY02E30/30
- WIPO fieldEngines, pumps, turbines
- WIPO sectorMechanical engineering
Abstract
A reduced-temperature method for treatment of a fuel element is described. The method includes molten salt treatment of a fuel element with a nitrate salt. The nitrate salt can oxidize the outer graphite matrix of a fuel element. The method can also include reduced temperature degradation of the carbide layer of a fuel element and low temperature solubilization of the fuel in a kernel of a fuel element.
Source: USPTO / EPO open patent data. Objective bibliographic and citation counts.