Studying the Pipeline Crack Growth in the Analysis of Nuclear Power Plant Internal Flooding and Estimating the Maximum Possible Leak Rate

Oleg Goryunov, Aleksandr Sovgirya, Nadezhda Sovgirya
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Abstract

Regulations concerned with the deterministic analysis of the impact of flooding on the NPP safety stipulate the need to evaluate the degradation degree of defense-in-depth (DiD) levels. The results of this analysis serve as input data for the probabilistic safety assessment (PSA) and selection of technical solutions. To estimate the flooding zone and the list of dependent failures, it is necessary to postulate the size of a pipeline or tank leak. The leak flowrate has an essential effect on the analysis result: the flooded zone size, the list of failed equipment components, and the characteristics of protective measures. The currently effective Federal Codes and Regulations of the Russian Federation do not stipulate procedures for estimating the consequences of flooding in the framework of a deterministic approach, and the use of foreign calculation procedures (ANSI / ANS-58-2, NUREG / CR-3464) yields ambiguous results. The conservatism level of foreign approaches is evaluated taking into account the laws of fracture mechanics. To this end, the maximum allowable sizes of defects in pipelines of various standard sizes that do not lead to a guillotine rupture and limit the maximum flowrate values are estimated. The results of the comparative analysis and calculations will be applied as part of the safety justification of Russian and foreign NPP projects.
核电厂内淹分析中管道裂缝扩展研究及最大可能泄漏率估算
有关洪水对核电站安全影响的确定性分析的法规规定需要评估纵深防御水平的退化程度。该分析结果可作为概率安全评估(PSA)和技术解决方案选择的输入数据。为了估计淹水区和相关故障列表,有必要假设管道或储罐泄漏的大小。泄漏流量对分析结果有至关重要的影响:淹水区大小、故障设备部件清单、防护措施特点。目前有效的俄罗斯联邦法典和条例没有规定在确定性方法框架内估计洪水后果的程序,并且使用国外计算程序(ANSI / ANS-58-2, NUREG / CR-3464)产生模糊的结果。考虑断裂力学规律,评价了国外方法的保守性水平。为此,估计了各种标准尺寸管道中不导致断头台破裂和限制最大流量值的缺陷的最大允许尺寸。比较分析和计算的结果将作为俄罗斯和外国核电站项目安全论证的一部分。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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