The Use of Bromine Trifluoride in the Recovery of Uranium from Mixtures of UO2 and MgO,

Abstract

A method is described for recovery of uranium from UO2-MgO ceramic fuel material by the use of bromine trifluoride. Recovery of 99.8 per cent uranium from pressed-sintered UO2-MgO was accomplished by grinding the material to 6 micron particle size, wetting with bromine and boiling with BrF3 for 3 hours. A study of particle size vs uranium recovery was made. This report is based upon studies conducted for the Atomic Energy Commission under Contract AT-11-1-GEN-8.

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Document Details

Document Type
Technical Report
Publication Date
Jun 10, 1953
Accession Number
ADA316364

Entities

People

  • F. D. Rosen

Organizations

  • Oak Ridge National Laboratory

Tags

Communities of Interest

  • Weapons Technologies

DTIC Thesaurus Topics

  • Boric Acids
  • Ceramic Materials
  • Chemical Analysis
  • Chemistry
  • Efficiency
  • Energy
  • Fluorine Compounds
  • Graphitic Materials
  • Materials
  • Materials Laboratories
  • Materials Processing
  • Materials Science
  • Nuclear Energy
  • Particle Size
  • Silica Glass
  • Sintering
  • United States

Readers

  • Combustion science or combustion engineering.
  • Manufacturing Engineering.
  • Nuclear Non-Proliferation and International Security