Processing fissile material mixtures containing zirconium and/or carbon
Abstract
A method of processing spent TRIZO-coated nuclear fuel may include adding fluoride to complex zirconium present in a dissolved TRIZO-coated fuel. Complexing the zirconium with fluoride may reduce or eliminate the potential for zirconium to interfere with the extraction of uranium and/or transuranics from fission materials in the spent nuclear fuel.
- Inventors:
- Issue Date:
- Research Org.:
- DOENE (USDOE Office of Nuclear Energy, Science and Technology (NE) (United States))
- Sponsoring Org.:
- USDOE
- OSTI Identifier:
- 1086795
- Patent Number(s):
- 8475747
- Application Number:
- 12/484,561
- Assignee:
- U.S. Department of Energy (Washington, DC)
- Patent Classifications (CPCs):
-
B - PERFORMING OPERATIONS B01 - PHYSICAL OR CHEMICAL PROCESSES OR APPARATUS IN GENERAL B01D - SEPARATION
Y - NEW / CROSS SECTIONAL TECHNOLOGIES Y10 - TECHNICAL SUBJECTS COVERED BY FORMER USPC Y10T - TECHNICAL SUBJECTS COVERED BY FORMER US CLASSIFICATION
- DOE Contract Number:
- FC01-07NE24502
- Resource Type:
- Patent
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
Citation Formats
Johnson, Michael Ernest, and Maloney, Martin David. Processing fissile material mixtures containing zirconium and/or carbon. United States: N. p., 2013.
Web.
Johnson, Michael Ernest, & Maloney, Martin David. Processing fissile material mixtures containing zirconium and/or carbon. United States.
Johnson, Michael Ernest, and Maloney, Martin David. Tue .
"Processing fissile material mixtures containing zirconium and/or carbon". United States. https://www.osti.gov/servlets/purl/1086795.
@article{osti_1086795,
title = {Processing fissile material mixtures containing zirconium and/or carbon},
author = {Johnson, Michael Ernest and Maloney, Martin David},
abstractNote = {A method of processing spent TRIZO-coated nuclear fuel may include adding fluoride to complex zirconium present in a dissolved TRIZO-coated fuel. Complexing the zirconium with fluoride may reduce or eliminate the potential for zirconium to interfere with the extraction of uranium and/or transuranics from fission materials in the spent nuclear fuel.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2013},
month = {7}
}
Works referenced in this record:
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Dissolution of Zirconium-Coating Fuel Elements
patent, December 1961
- Horn, Frederick L.
- US Patent Document 3012849
Retention of fission product caesium in ZrC-coated fuel particles for high-temperature gas-cooled reactors
journal, June 2000
- Minato, Kazuo; Ogawa, Toru; Koya, Toshio
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Dissolution process for ZrO.sub.2 -UO.sub.2 -CaO fuels
patent, June 1976
- Paige, Bernice E.
- US Patent Document 3,965,237
Process for Reprocessing a Spent Nuclear Fuel and of Preparing a Mixed Uranium-Plutonium Oxide
patent-application, December 2007
- Baron, Pascal; Dinh, Binh; Masson, Michel
- US Patent Application 11/753182; 20070290178