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:
- Issue Date:
- Research Org.:
- Savannah River Site (SRS), Aiken, SC (United States)
- Sponsoring Org.:
- USDOE
- OSTI Identifier:
- 1399896
- Patent Number(s):
- 9793019
- Application Number:
- 14/226,458
- Assignee:
- Savannah River Nuclear Solutions, LLC
- Patent Classifications (CPCs):
-
Y - NEW / CROSS SECTIONAL TECHNOLOGIES Y02 - TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE Y02E - REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
G - PHYSICS G21 - NUCLEAR PHYSICS G21C - NUCLEAR REACTORS
- 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. 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 = {2017},
month = {10}
}
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Works referenced in this record:
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