| 摘要 |
<p>Disclosed is a zirconium alloy material for a nuclear power reactor core, falling within the technical field of special alloy materials, and comprising the following components in percentage by weight: 0.60-1.00% of Sn, 0.80-1.10% of Nb, 0.10-0.40% of Fe, 0-0.1% of Cu or Bi or Ge, 0-0.03% of Si or S, 0.06-0.15% of O, less than 0.008% of C, less than 0.006% of N and the balance being Zr. Based on a Zr-Sn-Nb system alloy, other components used for improving the performance of the alloy are added, and appropriate component contents thereof are selected, so that the performance of the alloy provided meets the requirements of high burnup of the nuclear power reactor on the structural materials of the core. A product prepared from this alloy improves uniform corrosion resistance in ex-core pure water, especially in a lithium hydroxide aqueous solution, and improves nodular corrosion resistance in high-temperature steam.</p> |
