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Zirflex process for PWR blanket fuel :

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

A study of dissolution of reactor fuels containing zirconium in a titanium vessel

Diffusion in body-centered cubic metals zirconium, vanadium, niobium, and tantalum

Effect of degree of vacuum on the slow-bend creep behavior of columbium-0.6% zirconium at 1000⁰C

Published Year

• 1960-1969 (5) *

Subject

• Zirconium (5) *
• Chemistry (2)
• Uranium (2)
• Alloys (1)
• Alloys--Stress corrosion (1)
• Alloys--Stress corrosion--Testing (1)
• Ammonium (1)
• Hydrogen peroxide (1)
• Niobium alloys (1)
• Nitrates (1)
• Nuclear fuels (1)
• Nuclear reactions (1)
• Nuclear reactors (1)
• Plutonium (1)
• Uranium fluorides (1)
• Vanadium alloys (1)
• Zircaloy-2 (1)

Author

• Clark, Walter Ernest, (1)
• Ferris, L. M. (1)
• Gens, T. A. (1)
• Gens, Theodore A. (1)
• Lundy, Ted Sadler. (1)
• Roche, T. K. (1)

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