Z3CN20.09M奥氏体不锈钢热老化冲击性能试验研究

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Experimental Study on Thermal Aging Impact Properties of Austenitic Stainless Steel Z3CN20.09M

1. China Guangdong Nuclear Power Suzhou Research Institute, Suzhou, Jiangshu, 215004, China;
2. Xi'an Technological University, Xi'an, 710032, China

摘要: 采用GB/T19748-2005钢材夏比V型缺口摆锤冲击试验仪器化试验方法,对压水堆核电厂用离心铸造Z3CN20.09M奥氏体不锈钢主管道样品进行了实验室热老化的冲击性能研究。冲击试验数据的统计分析表明,热老化对F_iu/F_m比值不产生影响,而对冲击载荷有显著影响,对冲击能量的影响则更为显著。透射电子显微分析表明,热老化导致铁素体中出现沉淀物,并引发了奥氏体中位错组态的改变。与热老化时间lg t之间也满足线性关系。
- 核电厂 /
- 热老化 /
- 铸造不锈钢 /
- 冲击性能 /
- 预测
Abstract: The impact property of the centrifugal casting austenite stainless steel Z3CN20.09M no effect on the ratio value Fu/F_m but a significant influence on the impact force and especially on the impact energy.TEM analysis indicates that the shape of dislocations in austenitic has changed,and precipitations have appeared in ferrite.Extrapolation prediction of the impact property is performed by the regression functions established in this study.
- Nuclear power plant /
- Thermal aging /
- Casting stainless steel /
- Impact property /
- Prediction