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

Consolidated edison fuel losses on exposure to irradiated and aerated Sulfex and Darex decladding solutions

Measurement of hazardous components of Darex process off-gas

New laboratory developments in the Zircex process

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

Zircex and modified zirflex processes for dissolution of 8% U-91% Zr-1% H TRIGA reactor fuel

Published Year

• 1960-1969 (6) *

Subject

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

Author

• Gens, T. A. (6) *
• Johns, E. R. (1)
• Jolley, R. L. (1)

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