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Zirflex process for PWR blanket fuel :

Recovery of uranium from DI (2-ethylhexyl) phosphoric acid (dapex) extractant with ammonium carbonate

Fused salt fuel processing in the ORNL volatility pilot plant

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

Processing of high-fired uranium dioxide fuels by a reduction - mercury extraction - oxidation process

A study of the kinetics of uranyl sulfate exchange with a strong base anion resin

Published Year

• 1960-1969 (6) *

Subject

• Chemistry (6) *
• Uranium (6) *
• Plutonium (2)
• Zirconium (2)
• Alloys (1)
• Alloys--Stress corrosion (1)
• Alloys--Stress corrosion--Testing (1)
• Ammonium (1)
• Ammonium carbonate (1)
• Fused salts (1)
• Hydrogen peroxide (1)
• Kinetics (1)
• Mercury (1)
• Nitrates (1)
• Nuclear fuels (1)
• Oxidation (1)
• Phosphoric acid (1)
• Pilot plants (1)
• Uranium as fuel (1)
• Uranium dioxide (1)
• Uranium fluorides (1)
• Zircaloy-2 (1)

Author

• Carr, W. H. (1)
• Dean, O. C. (1)
• Ferris, L. M. (1)
• Gens, T. A. (1)
• Hurst, F. J. (1)
• Messing, A. F. (1)
• Watson, J. S. (1)
• Whitmarsh, C. L. (1)

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