Alloy for improved corrosion resistance of nuclear reactor...

C - Chemistry – Metallurgy – 22 – C

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C22C 16/00 (2006.01) G21C 3/07 (2006.01) G21C 3/12 (2006.01)

Patent

CA 2170068

An alloy having improved resistance to corrosion and hydriding, and having adequate strength, fabricability and irradiation growth. These properties make the new alloy exceptionally suited for use in boiling water reactor components such as fuel channels, fuel cladding and fuel rod spacers. The class of alloys includes zirconium-based alloys having about 0.3-1.2% tin, about 0.6-1.4% chromium, about 0.05-0.7% iron, and the remainder substantially zirconium.

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