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Title: Low temperature chemical processing of graphite-clad nuclear fuels

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.
Inventors:
Issue Date:
OSTI Identifier:
1399896
Assignee:
Savannah River Nuclear Solutions, LLC SRS
Patent Number(s):
9,793,019
Application Number:
14/226,458
Contract Number:
AC09-08SR22470
Resource Relation:
Patent File Date: 2014 Mar 26
Research Org:
Savannah River Site (SRS), Aiken, SC (United States)
Sponsoring Org:
USDOE
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS

Works referenced in this record:

Process and Targets for Production of No-Carrier-Added Radiotin
patent-application, September 2011

Block-type HTGR spent fuel processing: CEA investigation program and initial results
journal, March 2006
  • Masson, Michel; Grandjean, Stéphane; Lacquement, Jerôme
  • Nuclear Engineering and Design, Vol. 236, Issue 5-6, p. 516-525
  • DOI: 10.1016/j.nucengdes.2005.11.021