| 摘要 |
A fuel rod for a nuclear reactor comprises a cladding 1 of zirconium-based alloy, on the internal surface of which is arranged a layer 2 of zirconium or other material with greater resistance to stress corrosion than the zirconium-based alloy in the cladding and consisting of zirconium containing at most 3 percent by weight of other substances. On the surface of this layer facing towards the centre of the cladding there is a protective layer 3 of a zirconium-based alloy containing 1.2-1.7 percent by weight of tin, 0.07-0.24 percent by weight of iron, 0.05-0.15 percent by weight of chromium, 0-0.08 percent by weight of nickel, and 0.09-0.16 percent by weight of oxygen, the remainder being zirconium and normally occurring impurities found in zirconium of reactor quality. <IMAGE> |
