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首页> 外文期刊>Nuclear engineering and technology >Development of Wall-Thinning Evaluation Procedure for Nuclear Power Plant Piping-Part 1: Quantification of Thickness Measurement Deviation
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Development of Wall-Thinning Evaluation Procedure for Nuclear Power Plant Piping-Part 1: Quantification of Thickness Measurement Deviation

机译:核电厂管道壁厚评估程序的开发-第1部分:厚度测量偏差的量化

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Pipe wall thinning by flow-accelerated corrosion and various types of erosion is a significant and costly damage phenomenon in secondary piping systems of nuclear power plants (NPPs). Most NPPs have management programs to ensure pipe integrity due to wall thinning that includes periodic measurements for pipe wall thicknesses using nondestructive evaluation techniques. Numerous measurements using ultrasonic tests (UTs; one of the nondestructive evaluation technologies) have been performed during scheduled outages in NPPs. Using the thickness measurement data, wall thinning rates of each component are determined conservatively according to several evaluation methods developed by the United States Electric Power Research Institute. However, little is known about the conservativeness or reliability of the evaluation methods because of a lack of understanding of the measurement error. In this study, quantitative models for UT thickness measurement deviations of nuclear pipes and fittings were developed as the first step for establishing an optimized thinning evaluation procedure considering measurement error. In order to understand the characteristics of UT thickness measurement errors of nuclear pipes and fittings, round robin test results, which were obtained by previous researchers under laboratory conditions, were analyzed. Then, based on a large dataset of actual plant data from four NPPs, a quantitative model for UT thickness measurement deviation is proposed for plant conditions. Copyright (C) 2016, Published by Elsevier Korea LLC on behalf of Korean Nuclear Society.
机译:在核电厂的二次管道系统中,由于流动加速腐蚀和各种腐蚀引起的管壁变薄是一种重大且代价高昂的损坏现象。大多数NPP都有管理程序来确保由于壁变薄而引起的管道完整性,包括使用无损评估技术定期测量管道壁厚。在核电厂计划内的停机期间,已使用超声波测试(UT;一种非破坏性评估技术)进行了许多测量。使用厚度测量数据,根据美国电力研究所开发的几种评估方法,保守地确定每个组件的壁变薄率。然而,由于缺乏对测量误差的了解,人们对评估方法的保守性或可靠性知之甚少。在这项研究中,建立核管和配件的UT厚度测量偏差的定量模型是建立考虑测量误差的优化稀化评估程序的第一步。为了了解核管和配件的UT厚度测量误差的特征,分析了以前的研究人员在实验室条件下获得的循环测试结果。然后,基于来自四个核电厂的大量实际工厂数据集,提出了针对工厂条件的UT厚度测量偏差的定量模型。版权所有(C)2016,由Elsevier Korea LLC代表韩国核协会出版。

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