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ANALYSIS OF A WELD OVERLAY TO ADDRESS FATIGUE CRACKING IN A STAINLESS STEEL NOZZLE

机译:焊接覆盖物分析,以解决不锈钢喷嘴疲劳裂缝

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For several decades the nuclear industry has used structural weld overlays (SWOL) to repair and mitigate cracking within pressurized water reactor (PWR) components such as nozzles, pipes and elbows. There are two known primary mechanisms that have led to cracking within PWR components. One source of cracking has been primary water stress corrosion cracking (PWSCC). Numerous SWOL repairs and mitigations were installed in the early 2000s to address PWSCC in components such as pressurizer nozzles. However, nearly all of the likely candidate components for SWOL repairs have now been addressed in the industry. The other cause for cracking has been by fatigue, which usually results from thermal cycling events such as leakage caused by a faulty valve close to the component. The PWR components of most concern for fatigue cracking are mainly stainless steel. Thus, ASME Section XI Code Case N-504-4 would be a likely basis for SWOL repairs of these components, although this Code Case was originally drafted to address stress corrosion cracking (SCC) in boiling water reactors (BWR). N-504-4 includes the requirements for the SWOL design and subsequent analyses to establish the design life for the overlay based on predicted crack growth after the repair. This paper presents analysis work performed using Code Case N-504-4 to establish the design life of a SWOL repair applied to a boron injection tank (BIT) line nozzle attached to the cold leg of an operating PWR. The overlay was applied to the nozzle to address flaws found within the stainless steel base metal during inservice examination. Analyses were performed to calculate the residual stresses resulting from the original fabrication and the subsequent SWOL repair. In addition, post-SWOL operating stresses were calculated to demonstrate that the overlay does not invalidate the ASME Section III design basis for the nozzle and attached pipe. The operating and residual stresses were also used for input to a fatigue crack growth (FCG) analysis in order to establish the design life of the overlay. Lastly, the weld shrinkage from the application of overlay was evaluated for potential impact on the attached piping, restraints and valves within the BIT line. The combined analyses of the installed SWOL provide a basis for continued operation for the remaining life of the plant.
机译:数十年来,核工业中使用的结构堆焊(SWOL),以修复和减轻压水反应堆(PWR)的部件如喷嘴,管道,弯管内开裂。有迹象表明,导致PWR组件中开裂两个已知的主要机制。开裂的一个来源是主水应力腐蚀裂纹(PWSCC)。众多SWOL修理和缓解分别安装在21世纪初至地址PWSCC在组分如加压喷嘴。然而,在业内几乎所有的SWOL修理可能的候选组件现在已经解决。另一个原因用于裂化已经由疲劳,这通常由热循环事件等引起的故障阀靠近部件泄漏造成的。为疲劳开裂最为关注的PWR成分主要不锈钢。因此,ASME XI节代码情况下,N-504-4将这些组件的SWOL修理一个可能的基础,尽管今典案例最初起草地址应力腐蚀沸水反应堆(BWR)开裂(SCC)。的N- 504-4包括用于SWOL设计和后续分析以建立设计寿命为基于所述修复后的预测裂缝生长的覆盖要求。使用代码情况下,n-504-4建立施加到附接至操作PWR的冷段硼注入箱(BIT)线喷嘴SWOL修复的设计寿命本文呈现分析工作执行。所述覆盖物施加到喷嘴,以在役检查期间不锈钢母材中发现的地址的缺陷。进行分析,以计算从原来的制造和随后的修SWOL产生的残余应力。此外,计算后SWOL操作应力,以证明覆盖并不能否定的喷嘴和连接管中的ASME第三节设计依据。操作和残余应力也以建立覆盖层的设计寿命用于输入到疲劳裂纹扩展(FCG)分析。最后,从覆盖层的应用程序中的焊缝收缩评价对位线中的管道连接,约束和阀的潜在影响。安装SWOL的联合分析提供了工厂的剩余寿命持续经营的基础。

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