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

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.

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

Citation Formats

Pierce, Robert A. Low temperature chemical processing of graphite-clad nuclear fuels. United States: N. p., 2017. Web.
Pierce, Robert A. Low temperature chemical processing of graphite-clad nuclear fuels. United States.
Pierce, Robert A. Tue . "Low temperature chemical processing of graphite-clad nuclear fuels". United States. doi:. https://www.osti.gov/servlets/purl/1399896.
@article{osti_1399896,
title = {Low temperature chemical processing of graphite-clad nuclear fuels},
author = {Pierce, Robert A.},
abstractNote = {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.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Tue Oct 17 00:00:00 EDT 2017},
month = {Tue Oct 17 00:00:00 EDT 2017}
}

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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