超臨界水反應器(supercritical water-cooled reactor, SCWR)為第四代核能反應器之一，其操作環境高於水的臨界點，溫度必須超過374℃且壓力高於22.1 MPa。相對於現今輕水式反應器，超臨界水反應器的設計簡化使得安全性提高且降低成本，且超臨界水反應器操作在相當高溫的環境，因而提供相當高的熱效率，大約為45%(現今輕水式反應器熱效率約為33%)。
超臨界水所表現出的物理性質和溫度低於臨界點以下的液態水有很大的不同，因此材料在超臨界水環境下所表現的腐蝕行為成為一值得研究的題目。而本實驗將Inconel 625試片置於高壓釜內，實驗溫度測定於600℃，壓力在24.8 MPa (3600psi)，入水口溶氧濃度為8.3 ppm，透過腐蝕前後試片的單位面積質量改變量與微結構分析探討材料的腐蝕特性。於600℃之超臨界水環境下，相較於304L，Inconel 625在單位面積質量變化上並無明顯改變，利用300、600及1000小時的單位面積質量變化量得到一趨勢線，w^2.21=1.4×10^-5 t，符合拋物線律。另在表面發現8~9μm大小之孔蝕，推測孔蝕與原有的(Nb,Ti)C析出相有關。進一步分析得知氧化層呈現兩層的結構，外層為spinel Ni(Cr,Fe)2O4，內層為spinel Ni(Cr,Fe)2O4加上Cr2O3組成緻密連續的氧化層。經過輻射照射15dpa後再經過300小時600℃的腐蝕實驗後，氧化層與未經輻照之試片相比並無明顯變化，但母材之γ”有巨凝現象發生，在電子束入射方向B=[001]方向的長度約為原γ”的13倍。

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