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    核电站主管道不锈钢材料的热老化性能

    Thermal aging properties of stainless steel material for main pipeline of nuclear power plant

    • 摘要: 以国产和进口离心铸造奥氏体不锈钢为研究对象,采用加速热老化方法处理制备出6批不同热老化时间的试样。对比分析了两种材料热老化后的力学性能,利用光学显微镜、扫描电子显微镜及透射电子显微镜对试样的组织进行了系统表征。结果表明:两种材料的各项性能指标均符合RCCM-M3406标准要求;主管道材料的化学成分控制及显微组织优化会对其热老化性能产生显著影响;析出相的形成与发展速率与材料力学性能的下降速率并不一致。

       

      Abstract: Taking domestic and imported centrifugal casting austenitic stainless steel as the research object, six batches of samples with different thermal aging time were prepared by accelerated thermal aging method. The mechanical properties of the two materials after thermal aging were compared and analyzed. The microstructure of the samples was systematically characterized by optical microscope, scanning electron microscope and transmission electron microscope. The results show that the performance indexes of the two materials met the requirements of RCCM-M3406 standard. The chemical composition control and microstructure optimization of the main pipeline material would have a significant impact on its thermal aging performance. The formation and development rate of precipitates was not consistent with the decrease rate of mechanical properties of materials.

       

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