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SCWR候选不锈钢的高周疲劳行为研究 被引量:4

Study on High-Cycle Fatigue Behavior of Candidate Stainless Steels for SCWR
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摘要 采用旋转弯曲的加载方式对奥氏体不锈钢347、316Ti、310进行疲劳试验。试验环境为室温下空气中和550℃空气中。对疲劳断口进行扫描电镜(SEM)分析,根据试验数据绘制材料的应力-循环(S-N)曲线。结果表明,3种不锈钢疲劳极限大小顺序为347<316Ti<310,与静强度顺序一致;高温会加速试样的氧化,降低材料的疲劳寿命,347不锈钢的下降趋势最大,对温度最敏感;疲劳极限试验与经验公式计算值的比较表明,3种不锈钢具有较好的抗高周疲劳性能;疲劳过程为裂纹源产生、扩展和断裂,疲劳条带宽度在1μm左右的量级,最后断裂区具有韧窝特征,347不锈钢的韧窝中分布着数量较多的大小孔洞。 The fatigue experiments of commerce stainless steels including 347, 316Ti and 310 were conducted under bending and rotating loadings. The environments were at room temperature (RT) as well as at 550℃ in air. The fracture morphology was observed by SEM, and the S-N curves were processed according to the experimental data. The results indicate the fatigue limited stresses for the 3 stainless steels were in the order of 347〈316Ti〈310, which consistent with the order of their tensile strength. Elevated temperature would accelerate the oxidation and therefore the fatigue life would decrease, among them 347 was more sensitive to temperature with the maximum decreasing tendency. All the 3 stainless steels have good resistance to high cycle fatigue when comparing their experimental data with the calculated value from the empirical formula. The fracture morphology presents areas of crack initiation, crack growth and fracture, the width of fatigue ripples is about μ m, the fracture area has much dimples, and 347 presents much cavities of different sizes in dimples.
出处 《核动力工程》 EI CAS CSCD 北大核心 2013年第1期150-156,共7页 Nuclear Power Engineering
关键词 超临界水冷堆 结构材料 不锈钢 高周疲劳 SCWR, Structural materials, Stainless steel, High cycle fatigue
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