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《Nuclear Power Engineering》 2010-01
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Experimental Study on Thermal Aging Impact Properties of Austenitic Stainless Steel Z3CN20.09M

XUE Fei1,SHU Guo-gang1,TI Wen-xin1,YU Wei-wei1,MENG Xin-ming1 LIU Jing-nan2,SHI Chong-zhe2,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 2.Xi’an Technological University,Xi’an,710032,China)  
The impact property of the centrifugal casting austenite stainless steel Z3CN20.09M 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.
【CateGory Index】: TL34
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