摘要
研究了不同含量的Zr-Fe-Cr合金的显微组织及其在500℃,10.3MPa过热蒸汽中的耐腐蚀性能。结果表明,Zr-Fe-Cr合金经过真空熔炼、β淬火、真空包覆热轧和冷轧,以及真空退火处理得到的组织主要为α-Zr基体和弥散分布的Zr(Cr,Fe)2粒子。在500℃,10.3MPa过热水蒸汽中,含有少量合金元素的Zr-0.2Fe-0.1Cr和Zr-4合金会发生疖状腐蚀,而含有适当Fe、Cr的Zr-Fe-Cr合金为均匀腐蚀。Zr-1.0Fe-0.6Cr合金耐蚀性最好,其耐过热蒸汽腐蚀能力优于N18和Zr-4合金;含Fe、Cr元素不同的锆合金试样由于成分不同,耐腐蚀性能也有明显差别,说明调整合金成分是改善锆合金在500℃,10.3MPa过热蒸汽中耐腐蚀性能的主要途径。
The microstructure and corrosion behaviors of Zr-xFe-yCr alloys have been investigated in the superheated steam of 500℃/10.3 MPa. The results show that the composition of Zr-Fe-Cr alloy after vacuum melting, 13 quenching, vacuum covered hot and cold rolling, and vacuum annealing are α-Zr base and dispersed Zr （ Cr, Fe ） 2 particles. A nodular corrosion takes place on the Zr-4 and Zr-0.2Fe-0.1Cr specimens, but uniform corrosions occur on the Zr-Fe-Cr alloys with appropriate Fe and Cr, in the 500℃ and 10.3 MPa superheated steam. The Zr-1.0Fe-0.6Cr specimens have the best corrosion resistance, and its corrosion resis- tance in the superheated steam is better than that of N18 and Zr-4 alloys. The alloy specimens with different contents of Fe and Cr are with quite different corrosion resistances, which indicates that the composition of zirconium alloys is the key factor to improve the corrosion resistance in 500℃/10.3 MPa.
出处
《核动力工程》
EI
CAS
CSCD
北大核心
2009年第5期58-61,共4页
Nuclear Power Engineering
基金
核燃料及材料国家级重点实验室项目(9140C7004040903)
中国博士后科学基金(20090451426)
