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Modified zirflex process for dissolution of 1-10% U-Zr alloy fuels in aqueous NH₄F-NH₄NO₃-H₂O₂ :laboratory development

An oxyhydrochlorination process for preparing uranium-molybdenum reactor fuels for solvent extraction :laboratory development

Published Year

• 1960-1969 (2)

Subject

• Uranium (2) *
• Alloys (1)
• Alloys--Stress corrosion (1)
• Alloys--Stress corrosion--Testing (1)
• Ammonium (1)
• Chemistry (1)
• Hydrogen peroxide (1)
• Nitrates (1)
• Nuclear reactors (1)
• Plutonium (1)
• Solvent extraction (1)
• Zirconium (1)

Author

• Gens, T. A. (2) *

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