论文部分内容阅读
本文介绍了国产锆-2、锆-4合金在温度大于300℃的水或蒸汽中的腐蚀——氧化与吸氢;认为两种合金耐氧化性能相似,在反应堆工质中使用,具有足够的耐蚀性。水中添加少量氢氧化锂(含锂1—2ppm)或硼酸(含硼800ppm),对合金腐蚀无明显影响。在高温水中,锆-4在腐蚀300天后的吸氢增重约为锆-2的1/3—1/2;而在341℃蒸汽中,锆-4减少吸氢的优越性并不明显。水中加氢增加了锆-4的吸氢速率,但并没有达到妨碍使用的程度。预生氧化膜不能改善合金的耐长期腐蚀性能。具有热流的锆合金管与不锈钢定位架接触处的隙缝会导致危险的局部腐蚀,但在中性水条件下,腐蚀深度很浅,并不影响锆合金的长期使用。
In this paper, the corrosion-oxidation and hydrogen absorption of domestic zirconium-2 and zirconium-4 alloys in water or steam at temperatures above 300 ℃ are introduced. It is considered that the two alloys have similar oxidation resistance and are used in reactor fluids with sufficient Corrosion resistance. Add a small amount of lithium hydroxide water (containing lithium 1-2ppm) or boric acid (boron 800ppm), no significant effect on alloy corrosion. In high temperature water, zirconium-4 after 300 days of corrosion hydrogen absorption weight gain is about 1 / 3-1 / 2 zirconium -2; and 341 ℃ steam, zirconium-4 to reduce the superiority of hydrogen absorption is not obvious. Hydrogenation in water increases the rate of hydrogen uptake by zirconium-4 but does not reach the point of impeding the use. Pre-oxide film can not improve the long-term corrosion resistance of the alloy. Zirconium alloy tubes with a hot flow contact with the stainless steel spacer at the location of the gap will lead to dangerous local corrosion, but in neutral water conditions, the corrosion depth is very shallow, does not affect the long-term use of zirconium alloys.