核电站蒸汽发生器传热管用Inconel合金在高温高压水中的腐蚀行为研究

Corrosion Behavior of Inconel Alloys of Nuclear Power Steam Generator Tube in High-temperature and High-pressure Water

研究了核电站蒸汽发生器传热管用合金材料在模拟压水堆一回路水环境中形成的腐蚀氧化膜,首次获得了原位振动光谱。Inconel 600合金的拉曼谱中存在3个峰,540和610 cm-1拉曼峰源自于表面生成的Cr2O3氧化膜,670 cm-1峰对应于表面生成的Fe Cr2O4尖晶石产物,随着电位的增加,670 cm-1峰的相对强度显著增强。Inconel 690合金的表面氧化膜由Cr2O3构成,不含Ni O或尖晶石成份。Inconel 600合金发生应力腐蚀开裂(SCC)的敏感性与其表面氧化膜的变化存在关联性。Inconel 690合金尚未发现SCC现象,这与其表面生成的稳定的氧化膜有关。

In this study, we have acquired in-situ vibrational spectra of oxides formed on inconel alloys of steam generator tube in simulated primary water(PW) of pressurized water reactor(PWR).There are three Raman peaks for the oxidized Inconel 600. The peaks at 540 and 610 cm-1are attributed to a formation of Cr2O3, and 670 cm-1peak is corresponding to Fe Cr2O4 spinel. As the potential increases, the relative intensity of 670 cm-1peak increases. The surface film of Inconel 690 consisted of Cr2O3 solely. Stress corrosion cracking(SCC) of Inconel 600 is correlating with the changing of its surface film. A stable surface film formed on Inconel 690 might be responsible for its excellent SCC resistance.