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Title: 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:

Retention of fission product caesium in ZrC-coated fuel particles for high-temperature gas-cooled reactors
journal, June 2000