首页> 外文会议>International Colloquium on Mechanical Fatigue of Metals >Characterization of damage during low cycle fatigue of a 304L austenitic stainless steel as a function of environment (air, PWR environment) and surface finish (polished, ground)
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Characterization of damage during low cycle fatigue of a 304L austenitic stainless steel as a function of environment (air, PWR environment) and surface finish (polished, ground)

机译:304L奥氏体不锈钢低循环疲劳期间损伤的表征,作为环境(空气,PWR环境)和表面光洁度(抛光,地)

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304L austenitic stainless steel is notably used to manufacture pipes in primary cooling circuits of nuclear power plants operating at a temperature close to 300°C in a specific aqueous environment. Customarily, pipes are roughly polished, however, after some interventions, a few zones might be ground. Start-ups, shutdowns and operating transients of the reactor produce Low Cycle Fatigue (LCF) loadings with different strain rates. These solicitations and the modified surface finish create specific conditions whose effects must be taken into account. In order to understand if there is a joint influence of the PWR environment and surface roughness on the successive stages of fatigue damage leading to failure, fatigue tests were conducted at 300°C under a total strain amplitude of ± 0.6%. Two environments were used, laboratory air and simulated PWR primary aqueous environment. Two surface finishes were investigated, namely fine mechanical polishing and grinding (Rt of about 40 μm). The analysis of the damage process is based on data concerning crack density, crack length and striation spacing. The integration of the relation between the striation spacing and the strain intensity factor ΔK_ε, provides an estimation of crack propagation. It is confirmed that in PWR environment one striation can be considered as the crack advance during one fatigue cycle. Moreover, the specific crack front geometry observed in ground specimens and resulting from successive microcrack coalescences explains the reduction in fatigue life induced by grinding.
机译:304L奥氏体不锈钢可显着用于在特定含水环境中在接近300℃的温度下操作的核电厂的初级冷却电路中的管道。通常,管道大致抛光,但是,在一些干预之后,可能是几个区域。反应堆的启动,关机和操作瞬变产生具有不同应变速率的低循环疲劳(LCF)负载。这些诉讼和修改的表面光洁度创造了必须考虑其效应的特定条件。为了了解PWR环境的联合影响和在导致失效的疲劳损伤的连续阶段的联合影响,疲劳试验在300℃下在总应变幅度为±0.6%。使用了两种环境,实验室空气和模拟PWR原发水环境。研究了两种表面饰面,即精细的机械抛光和研磨(RO为约40μm)。损伤过程的分析基于有关裂缝密度,裂缝长度和抗条间距的数据。突变间隔和应变强度因子ΔK_ε之间的关系的积分提供了裂缝传播的估计。确认,在PWR环境中,在一个疲劳循环期间,可以将一种抗议视为裂缝进展。此外,在地面试样中观察到的特定裂纹前几何形状并由连续微裂纹聚合产生解释了研磨引起的疲劳寿命的降低。

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