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发明公开
CN102212719A 一种核反应堆用低锡锆合金材料 有权

一种核反应堆用低锡锆合金材料
摘要：
本发明公开了一种核反应堆用低锡锆合金材料，以所述低锡锆合金材料的总重量为基准，所述低锡锆合金由如0.8%～1.0%Nb；0.2%~0.5%Sn；0.2%～0.5%Fe；0.06%～0.14%O；0.1%～0.2%的Cr或V；以及余量为Zr组成，其中：Sn和Fe的重量百分比之和为0.5%～1.0%。本发明通过大量实验研究发现，在控制锆合金中Sn和Fe的重量百分比之和在一定范围内时，加入特定量的Cr或V能够大大减少合金焊缝处的腐蚀，由此可以提高核燃料组件的安全性、成本和效率，其中，V还能够改进合金的力学性能。整体上说，本发明的锆合金的耐腐蚀性能提高，可靠性更好。
摘要（英）：

The invention discloses a low-tin-zirconium alloy material for a nuclear reactor. On the basis of the total weight of the low-tin-zirconium alloy material, the low-tin-zirconium alloy comprises the following components in percentage by weight: 0.8-1.0% of Nb, 0.2-0.5% of Sn, 0.2-0.5% of Fe, 0.06-0.14% of O, 0.1-0.2% of Cr or V and the balance of Zr, wherein the sum of the weight percentage of Sn and Fe is 0.5-1.0%. In the invention, lots of experiments prove that corrosion at an alloy welding seam can be greatly reduced by adding Cr or V in a specific amount in the event of controlling the sum of the weight percentage of Sn and Fe in zirconium alloy in a certain range; therefore, the safety, the cost and the efficiency of nuclear fuel components can be improved; V is also used for improving mechanical property of the alloy; as a whole, the anticorrosion performance of the zirconium alloy in the invention is improved; and the reliability of the zirconium alloy is better.

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