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Low temperature chemical processing of graphite-clad nuclear fuels

United States Patent

9,793,019
October 17, 2017
View the Complete Patent at the US Patent & Trademark Office
Savannah River National Laboratory - Visit the Technology Transfer Website
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.
Pierce; Robert A. (Aiken, SC)
Savannah River Nuclear Solutions, LLC (Aiken, SC)
14/ 226,458
20170301423
March 26, 2014
STATEMENT AS TO RIGHTS TO INVENTIONS MADE UNDER FEDERALLY SPONSORED RESEARCH This invention was made with Government support under Contract No. DE-AC09-08SR22470 awarded by the United States Department of Energy. The Government has certain rights in the invention.