Abstract: 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.