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WALL THINNING ANALYSES FOR SECONDARY SIDE PIPING OF KOREAN NPPS USING CHECWORKS CODE

机译:韩国NPPS使用ChecWorks代码的次侧管道壁稀释分析

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Since the mid-1990s, nuclear power plants in Korea have experienced wall thinning, leaks, and ruptures of secondary side piping caused by flow-accelerated corrosion (FAC). The pipe failures have increased as operating time progresses. In order to prevent FAC-induced pipe failures and to develop an effective FAC management strategy, KEPRI and KOPEC, along with KHNP's support, have conducted a study for developing a systematic FAC management technology for all domestic nuclear power plants. As part of the study, FAC analyses were performed using CHECWORKS code. The analysis results were used to select components for inspection on each nuclear power plant. The site application feasibility of the analysis results was proven by comparisons of predicted and measured wear rates. This paper focuses on the introduction of the FAC analysis results for secondary side piping associated with three types of domestic nuclear power plants and the comparisons of predicted and measured wear rates. This paper also represents the comparisons of analysis results according to reactor types, power rates, and systems to facilitate the development of FAC management technology.
机译:自20世纪90年代中期以来,韩国的核电站经历了由流动加速腐蚀(FAC)引起的次侧管道的壁变薄,泄漏和破裂。随着操作时间的进展,管道故障增加。为了防止FAC诱导的管道故障并开发有效的FAC管理策略,KEPRI和KOPEC以及KHNP的支持,对所有国内核电站开发系统的FAC管理技术进行了研究。作为研究的一部分,使用ChecWorks代码进行FAC分析。分析结果用于选择对每个核电站检查的组件。通过预测和测量的磨损率的比较证明了分析结果的现场应用可行性。本文重点介绍了与三种类型的国内核电站相关的二次侧管道的FAC分析结果,以及预测和测量磨损率的比较。本文还表示根据反应堆类型,电力速率和系统的分析结果的比较,以促进FAC管理技术的发展。

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