期刊文献+

核电用铸造奥氏体不锈钢的热老化性能研究 被引量:2

Study on Thermal Aging Performance of Cast Austenite Stainless Steel in Nuclear Power Plant
下载PDF
导出
摘要 压水堆核电厂主管道用国产铸造奥氏体不锈钢(CASS)长期服役会面临着热老化问题。在400℃高温下开展CASS材料的加速热老化实验,采用夏比冲击试验获得了材料室温吸收能量随热老化时间延长的下降规律,采用扫描电镜观察到不同热老化时间冲击断口形貌的变化趋势。实验结果表明:经过15 000h的加速热老化实验,CASS材料的热老化程度逐渐达到饱和状态,吸收能量虽大幅下降,但仍能满足设计规范对CASS材料在未老化状态时的考核要求。 The domestic cast austenitic stainless steel(CASS)used for PWR main coolant lines faces thermal aging phenomenon during long-term service.The accelerated thermal aging experiment at elevated temperature of 400℃for CASS was carried out,the decrease regularity of absorbed energy for CASS at room temperature was obtained using Charpy impact test,and the variation trend of CASS's fracture surfaces of impact specimens at different aging time was investigated using scanning electron microscope.The experiment results show that after 15 000 hours of accelerated thermal aging,the domestic CASS gradually reaches a thermal aging saturation,and its absorbed energy reduces greatly,but still meets the assessment indicators for unaged state required by design specifications.
出处 《原子能科学技术》 EI CAS CSCD 北大核心 2014年第S1期502-505,共4页 Atomic Energy Science and Technology
关键词 核电厂主管道 铸造奥氏体不锈钢 热老化 加速试验 吸收能量 NPP main coolant lines cast austenite stainless steel thermal aging accelerated experiment absorbed energy
  • 相关文献

同被引文献10

引证文献2

相关作者

内容加载中请稍等...

相关机构

内容加载中请稍等...

相关主题

内容加载中请稍等...

浏览历史

内容加载中请稍等...
;
使用帮助 返回顶部