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Corrosion Fatigue of Austenitic Stainless Steels for Nuclear Power Engineering

机译:核电工程用奥氏体不锈钢的腐蚀疲劳

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Significant structural steels for nuclear power engineering are chromium-nickel austenitic stainless steels. The presented paper evaluates the kinetics of the fatigue crack growth of AISI 304L and AISI 316L stainless steels in air and in corrosive environments of 3.5% aqueous NaCl solution after the application of solution annealing, stabilizing annealing, and sensitization annealing. Comparisons were made between the fatigue crack growth rate after each heat treatment regime, and a comparison between the fatigue crack growth rate in both types of steels was made. For individual heat treatment regimes, the possibility of the development of intergranular corrosion was also considered. Evaluations resulted in very favourable corrosion fatigue characteristics of the 316L steel. After application of solution and stabilizing annealing at a comparable ? K level, the fatigue crack growth rate was about one half compared to 304L steel. After sensitization annealing of 316L steel, compared to stabilizing annealing, the increase of crack growth rate during corrosion fatigue was slightly higher. The obtained results complement the existing standardized data on unconventional characteristics of 304L and 316L austenitic stainless steels.
机译:核电工程中重要的结构钢是铬镍奥氏体不锈钢。本文应用溶液退火,稳定退火和敏化退火后,评估了AISI 304L和AISI 316L不锈钢在空气和3.5%NaCl水溶液中的腐蚀环境下的疲劳裂纹扩展动力学。比较各热处理方式后的疲劳裂纹扩展率,并对两种钢的疲劳裂纹扩展率进行比较。对于单独的热处理方案,还考虑了发生晶间腐蚀的可能性。评估得出316L钢具有非常良好的腐蚀疲劳特性。固溶后并在相当的温度下稳定退火K水平下,疲劳裂纹扩展速度是304L钢的一半。与稳定化退火相比,对316L钢进行敏化退火后,腐蚀疲劳过程中裂纹扩展速率的增加略高。所得结果补充了有关304L和316L奥氏体不锈钢非常规特性的现有标准化数据。

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