Zirconium alloy barrier having improved corrosion resistance

Details Zirconium alloy barrier having improved corrosion resistance Zirconium alloy barrier having improved corrosion resistance

G - Physics

21

C

359/67, 117/70

G21C 3/06 (2006.01) B32B 15/01 (2006.01) G21C 3/20 (2006.01)

Patent

CA 1209726

ZIRCONIUM ALLOY BARRIER HAVING IMPROVED CORROSION RESISTANCE ABSTRACT OF THE DISCLOSURE A nuclear fuel element for use in the core of a nuclear reactor has a composite cladding container having a substrate and a dilute zirconium alloy liner bonded to the inside surface of the substrate. The dilute zirconium alloy liner forms about 1 to about 20 percent of the thickness of the cladding and is comprised of zirconium and a metal selected from the group consisting of iron, chromium, iron plus chromium, and copper. The dilute zirconium alloy liner shields the substrate from impurities or fission products from the nuclear fuel material and protects the substrate from stress corrosion and stress cracking. The dilute zirconium alloy liner displays greater corrosion resistance, especially to oxidation by hot water or steam than unalloyed zirconium. The substrate material is selected from conventional cladding materials, and preferably is a zirconium alloy.

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