skip to main content
DOE Patents title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: Method of separating and recovering uranium from aluminum-clad metallic nuclear fuel

Abstract

According to one aspect of the invention, a method for separating and recovering uranium from a nuclear fuel element. The method includes immersing a nuclear fuel element containing nuclear fuel and cladding in a molten metal. The nuclear fuel includes uranium. The cladding is selectively dissolved from the nuclear fuel element when immersed in the molten metal. The nuclear fuel is separated from the cladding. The method then includes loading the nuclear fuel into a permeable basket that is electrically configured as an anode of an electrolytic cell. There are also a molten salt electrolyte and a cathode in the electrolytic cell. Then, the method includes applying an electric charge across the electrolytic cell. The molten salt electrolyte selectively transfers uranium from the anode to the cathode.

Inventors:
;
Issue Date:
Research Org.:
Idaho National Lab. (INL), Idaho Falls, ID (United States)
Sponsoring Org.:
USDOE
OSTI Identifier:
1576313
Patent Number(s):
10,418,138
Application Number:
16/166,232
Assignee:
U.S. Department of Energy (Washington, DC)
DOE Contract Number:  
AC07-05ID14517
Resource Type:
Patent
Resource Relation:
Patent File Date: 2018 Oct 22
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; 42 ENGINEERING; 38 RADIATION CHEMISTRY, RADIOCHEMISTRY, AND NUCLEAR CHEMISTRY

Citation Formats

Herrmann, Steven, and Norbash, Kevin. Method of separating and recovering uranium from aluminum-clad metallic nuclear fuel. United States: N. p., 2019. Web.
Herrmann, Steven, & Norbash, Kevin. Method of separating and recovering uranium from aluminum-clad metallic nuclear fuel. United States.
Herrmann, Steven, and Norbash, Kevin. Tue . "Method of separating and recovering uranium from aluminum-clad metallic nuclear fuel". United States. https://www.osti.gov/servlets/purl/1576313.
@article{osti_1576313,
title = {Method of separating and recovering uranium from aluminum-clad metallic nuclear fuel},
author = {Herrmann, Steven and Norbash, Kevin},
abstractNote = {According to one aspect of the invention, a method for separating and recovering uranium from a nuclear fuel element. The method includes immersing a nuclear fuel element containing nuclear fuel and cladding in a molten metal. The nuclear fuel includes uranium. The cladding is selectively dissolved from the nuclear fuel element when immersed in the molten metal. The nuclear fuel is separated from the cladding. The method then includes loading the nuclear fuel into a permeable basket that is electrically configured as an anode of an electrolytic cell. There are also a molten salt electrolyte and a cathode in the electrolytic cell. Then, the method includes applying an electric charge across the electrolytic cell. The molten salt electrolyte selectively transfers uranium from the anode to the cathode.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2019},
month = {9}
}

Patent:

Save / Share:

Works referenced in this record:

Pyroelectrochemical process for reprocessing irradiated nuclear fuels
patent, October 1981