Research on Corrosion Fatigue Behavior in High Temperature Pressurized Water of Z3CN20-09M Stainless

来源 :第三届核电厂材料与安全可靠性国际研讨会 (3rd MRNPP Symposium) | 被引量 : 0次 | 上传用户:fiona_01
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  Cast austenite stainless steels(CASS)were widely used in the primary circuit piping of pressurized water nuclear reactors(PWRs).Low cycle fatigue tests of CASS Z3CN20-09M were performed in room temperature in air and high temperature pressurized water.Effects of high temperature water and stain rate on fatigue life and fatigue behaviors were discussed.The results indicated that the fatigue life of Z3CN20-09M steel decrease due to the effect of test high temperature water.Fatigue life in high temperature water depends on strain rate,its shortened as the strain rate decreases,and this behavior is more significant in the high strain amplitudes.Lots of secondary cracks occur on fatigue specimens surface in high temperature water.Cracks show tortuous behavior,and cracks were coalescence and branch deflection each other,showing the typical characteristics of multiple cracks.
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