| 摘要 |
A zirconium alloy for nuclear fuel components such as cladding tubes, spacers, boxes, etc., with improved properties with respect to the absorption of hydrogen released during the corrosion, in combination with good strength and creep properties. The alloy contains zirconium and tin, iron, nickel, chromium, and silicon with a total content of at least 0.54 per cent by weight and at most 2.15 per cent by weight, of which the content of tin is at least 0.03 %, the content of iron at least 0.07 %, the content of nickel at least 0.03 %, the content of chromium at least 0.05 %, and the content of silicon at least 0.005 % and 0.15-0.30 % vanadium and 0.015-0.30 % niobium. |
