Low Temperature Chemical Processing of Graphite-Clad Nuclear Fuels
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United States of America Patent
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Oct 17, 2017
Grant Date -
Oct 19, 2017
app pub date -
Mar 26, 2014
filing date -
Mar 26, 2014
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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.
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