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
orrosion Behavior of Inconel Alloys of Nuclear Power Steam Generator Tube in High-temperature and High-pressureWater
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。Inconel600合金的拉曼谱中存在3个峰，540和610cm-1拉曼峰源自于表面生成的Cr2O3氧化膜，670cm-1峰对应于表面生成的FeCr2O4尖晶石产物，随着电位的增加，670cm-1峰的相对强度显著增强。Inconel690合金的表面氧化膜由Cr2O3构成，不含NiO或尖晶石成份。Inconel600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。Inconel690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-1 are attributed to a formation of Cr2O3, and 670 cm-1 peak is corresponding to FeCr2O4 spinel. As the potential increases, the relative intensity of 670 cm-1 peak 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.
汪峰、ThomasM.Devine
原子能技术基础理论冶金技术
高温高压水蒸汽发生器传热管因科镍合金腐蚀行为
汪峰,ThomasM.Devine.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[EB/OL].(2023-03-31)[2025-08-02].https://chinaxiv.org/abs/202303.10675.点此复制
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