Inconel-690合金在核电厂水质环境中的均匀腐蚀性能研究

Research on Uniform Corrosion of Inconel 690 Alloy for Stream Generator in Nuclear Plant Water Environment

模拟核电厂水质环境,采用动水腐蚀回路研究3种蒸汽发生器传热管商用690材料的均匀腐蚀性能以及氧化膜的特性,并分别采用国家标准和美国标准对材料均匀腐蚀速率和腐蚀产物释放速率进行评价。结果表明:690合金管在核电厂水质环境中具有极低的腐蚀速率和腐蚀产物释放速率,日本住友管的腐蚀性能略优于宝钢管。

Under the stimulated nuclear plant water environment, corrosion property and oxide film characteristics of three kinds of commercial 690 alloys for steam generators were studied in the flow-water corrosion loop. Meanwhile, the general corrosion rate and corrosion product release rate were also estimated using Chinese standard and American standard respectively. The results show that： under the stimulated nuclear plant water environment, 690 alloy tube exhibits very low corrosion rate and corrosion product release rate, and the corrosion performance of Japan Sumitomo 690 alloy tube is better than that of Baosteel 690 alloy tube.