| 摘要 |
Nuclear fuel element for use in the core of a nuclear reactor having a composite container which has a substrate and a lining made of a dilute zirconium alloy, the latter being joined to the inner surface of the substrate. The lining has a thickness of about 1 to 20% of the thickness of the composite container and it contains about 0.1 to about 0.5 and preferably about 0.2 to about 0.4% by weight of niobium, the remainder being zirconium. The dilute zirconium alloy lining protects the substrate against contamination and fission products from the nuclear fuel material and protects the substrate against stress corrosion and stress corrosion cracking. The lining has a greater corrosion resistance, in particular towards oxidation by hot water and steam, than non-alloyed zirconium. The material for the substrate is selected from standard sheathing materials and is preferably a zirconium alloy having a higher alloying content than the dilute zirconium alloy of the lining. <IMAGE>
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