Zr-4合金和M5锆合金是国内核电站最常用的核反应堆包壳材料，其耐腐蚀性能是一项重要的检测指标。在高压釜蒸汽腐蚀实验中，为了确认腐蚀数据的有效性，每釜应随检测样品放置对比样。针对Zr-4合金作为对比样时的酸洗预处理工艺开展实验，研究是否酸洗及酸洗工艺对其腐蚀增重的影响，以期为建立Zr-4合金对比样规范提供科学的试验方法。研究结果表明，酸洗预处理会明显影响Zr-4合金的腐蚀增重及其标准偏差，未经酸洗处理的Zr-4合金对比样的腐蚀增重较稳定，标准偏差及增重极差值均低于经酸洗预处理的对比样。
Zr-4 alloy and M5 zirconium alloy are the most useful cladding materials in nuclear power reactor .It is an important testing index for their corrosion resistance .In order to confirm the validity of corrosion weight gain data , it must be put contrast samples in autoclave at the experiment of steam corrosion .In this paper , acid washing pretreat-ment technologies for Zr-4 alloy were done , and the influence of acid washing pretreatment on steam corrosion weight gain was tested .It would be a scientific method for establishing Zr-4 alloy standard as contrast samples .The results show that the acid washing process has significant effect on weight gain and standard deviations of Zr -4 alloy.Samples which unwashed have stable weight gain and the standard deviation are less than the acid -washed samples .
参考文献
| [1] | 魏晓伟,沈保罗.核反应堆中防护包壳的研究进展[J].稀有金属,2002(04):304-306. |
| [2] | ASTM G2/G2M-06.Standard Test Method for Corrosion Testing of Products of Zirconium, Hafnium, and Their Alloys in Water at 680 ℉(360 ℃) or in Steam at 750 ℉(400 ℃)[S].West Conshohocken:ASTM International,2006. |
- 下载量()
- 访问量()
- 您的评分：
-
10%
-
20%
-
30%
-
40%
-
50%