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Title: Separation of uranium from (Th,U)O.sub.2 solid solutions

Abstract

Uranium is separated from mixed oxides of thorium and uranium by a pyrometallurgical process in which the oxides are mixed with a molten chloride salt containing thorium tetrachloride and thorium metal which reduces the uranium oxide to uranium metal which can then be recovered from the molten salt. The process is particularly useful for the recovery of uranium from generally insoluble high-density sol-gel thoria-urania nuclear reactor fuel pellets.

Inventors:
 [1];  [2]
  1. Ames, IA
  2. Arvada, CO
Issue Date:
Research Org.:
Ames Lab., Ames, IA (United States); Iowa State Univ., Ames, IA (United States)
OSTI Identifier:
862652
Patent Number(s):
3982928
Assignee:
United States of America as represented by United States Energy (Washington, DC)
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:  
W-7405-ENG-82
Resource Type:
Patent
Country of Publication:
United States
Language:
English
Subject:
separation; uranium; solid; solutions; separated; mixed; oxides; thorium; pyrometallurgical; process; molten; chloride; salt; containing; tetrachloride; metal; reduces; oxide; recovered; particularly; useful; recovery; insoluble; high-density; sol-gel; thoria-urania; nuclear; reactor; fuel; pellets; mixed oxide; salt containing; fuel pellet; uranium oxide; fuel pellets; nuclear reactor; molten salt; particularly useful; reactor fuel; solid solution; uranium metal; chloride salt; metallurgical process; mixed oxides; solid solutions; molten chloride; /75/423/976/

Citation Formats

Chiotti, Premo, and Jha, Mahesh Chandra. Separation of uranium from (Th,U)O.sub.2 solid solutions. United States: N. p., 1976. Web.
Chiotti, Premo, & Jha, Mahesh Chandra. Separation of uranium from (Th,U)O.sub.2 solid solutions. United States.
Chiotti, Premo, and Jha, Mahesh Chandra. Tue . "Separation of uranium from (Th,U)O.sub.2 solid solutions". United States. https://www.osti.gov/servlets/purl/862652.
@article{osti_862652,
title = {Separation of uranium from (Th,U)O.sub.2 solid solutions},
author = {Chiotti, Premo and Jha, Mahesh Chandra},
abstractNote = {Uranium is separated from mixed oxides of thorium and uranium by a pyrometallurgical process in which the oxides are mixed with a molten chloride salt containing thorium tetrachloride and thorium metal which reduces the uranium oxide to uranium metal which can then be recovered from the molten salt. The process is particularly useful for the recovery of uranium from generally insoluble high-density sol-gel thoria-urania nuclear reactor fuel pellets.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1976},
month = {9}
}

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