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Z3CN20.09M奥氏体不锈钢热老化冲击性能试验研究
引用本文:薛飞,束国刚,遆文新,余伟炜,蒙新明,刘江南,石崇哲.Z3CN20.09M奥氏体不锈钢热老化冲击性能试验研究[J].核动力工程,2010,31(1).
作者姓名:薛飞  束国刚  遆文新  余伟炜  蒙新明  刘江南  石崇哲
作者单位:1. 中国广东核电集团苏州热工研究院,江苏苏州,215004
2. 西安工业大学,西安,710032
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Fiu/Fm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。

关 键 词:核电厂  热老化  铸造不锈钢  冲击性能  预测

Experimental Study on Thermal Aging Impact Properties of Austenitic Stainless Steel Z3CN20.09M
XUE Fei,SHU Guo-gang,TI Wen-xin,YU Wei-wei,MENG Xin-ming,LIU Jing-nan,SHI Chong-zhe.Experimental Study on Thermal Aging Impact Properties of Austenitic Stainless Steel Z3CN20.09M[J].Nuclear Power Engineering,2010,31(1).
Authors:XUE Fei  SHU Guo-gang  TI Wen-xin  YU Wei-wei  MENG Xin-ming  LIU Jing-nan  SHI Chong-zhe
Abstract:The impact property of the centrifugal casting austenite stainless steel Z3CN20.09M manufactured by France was studied with Charpy impact test, which is used as the primary loop pipe in PWR nuclear power plant. Statistical analysis of the instrumental impact test data indicates that thermal ageing has no effect on the ratio value Fu/Fm 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.
Keywords:Nuclear power plant  Thermal aging  Casting stainless steel  Impact property  Prediction
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