首页> 外文会议>ASME(American Society of Mechanical Engineers) Pressure Vessels and Piping Conference 2006 vol.6: Materials and Fabrication >DELAYED HYDRIDE CRACKING INITIATION AT SIMULATED DEBRIS FRETTING FLAWS IN Zr-2.5Nb ALLOYS
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DELAYED HYDRIDE CRACKING INITIATION AT SIMULATED DEBRIS FRETTING FLAWS IN Zr-2.5Nb ALLOYS

机译:Zr-2.5Nb合金中模拟碎屑微动缺陷的延迟氢化物开裂

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Flaws in Zr-2.5Nb alloy pressure tubes in CANDU nuclear reactors are susceptible to a crack initiation and growth mechanism known as Delayed Hydride Cracking (DHC), which is a repetitive process that involves hydrogen diffusion, hydride precipitation, growth and fracture of the hydrided region at the flaw-tip. In-service flaw evaluation requires an analysis to demonstrate DHC will not initiate from the flaw. The work presented in this paper examines DHC initiation behavior from simulated debris fretting flaws. Groups of cantilever beam specimens containing V-notches with root radii of 15, 30 and 100 μm were prepared from two unirradiated pressure tubes hydrided to a nominal hydrogen concentration of 57 wt. ppm. The specimens were loaded to different stress levels that straddled the threshold value predicted by an engineering model, and subjected to multiple thermal cycles relevant to reactor operating conditions to form hydrides at the flaw-tip. Threshold conditions for DHC initiation were established for the flaw geometries and thermal cycling conditions used in this program. Test results indicate that the susceptibility to DHC initiation was affected by material variability and notch root radius. The results are also compared with model predictions.
机译:CANDU核反应堆中Zr-2.5Nb合金压力管中的缺陷易受称为延迟氢化物裂解(DHC)的裂纹萌生和扩展机制的影响,该过程涉及氢扩散,氢化物沉淀,氢化物的生长和破裂。尖端区域。在役缺陷评估需要进行分析,以证明DHC不会从缺陷中启动。本文介绍的工作从模拟碎片微动缺陷中检查了DHC的起爆行为。从两个未辐照的压力管氢化成标称氢浓度为57 wt。%,制备成组的包含V形缺口,根半径为15、30和100μm的悬臂梁样品。 ppm。样品被加载到跨越工程模型预测的阈值的不同应力水平,并经受与反应堆运行条件相关的多个热循环,从而在缺陷尖端形成氢化物。为该程序中使用的缺陷几何形状和热循环条件确定了DHC引发的阈值条件。测试结果表明,DHC引发的敏感性受到材料变异性和缺口根半径的影响。还将结果与模型预测进行比较。

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