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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

Other works cited in this record:

Production of Sodium Nitrate
patent, December 1950

Chemical Disintegration and Recovery of Uranium from Sintered Graphite-Uranium Compacts
patent, November 1965

Processes for the Dissolution of Uranium in Nitric Acid
patent-application, March 1966

Method of Reprocessing and/or Separating Nuclear Fuels
patent, May 1967

Method of Decomposing a Nuclear Fuel in a Fused Salt System by Using Nitric Oxide
patent, July 1968

Method of Treating Coated-Particle Nuclear-Reactor Fuels
patent, October 1968

Method for the Extraction of Materials Embedded in a Graphite Body
patent, January 1969

Automatic Toaster
patent, February 1969

Method of and Apparatus for the Treatment of Graphite-Coated Particles for Nuclear Reactors and the Like
patent, July 1969

Coated-Particle Fuel and Fertile Element for Nuclear Reactors and Method of Operating Same
patent, June 1972

Process for a gasification of graphite
patent, October 1980

Process for the separation of coated nuclear fuel particles from a graphitic matrix and installation for implementing the process
patent, March 1985

Heat-aided method for separating the graphite matrix from the nuclear fuel of nuclear reactor fuel elements
patent, March 1985

Method for disposing of radioactive graphite and silicon carbide in graphite fuel elements
patent, September 1995

Encapsulation of spent ceramic nuclear fuel
patent-application, January 2004

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

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