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Overview of the International Comparative Assessment Study of Pressurized Thermal-Shock in Reactor Pressure Vessels (RPV PTS ICAS)

机译:反应堆压力容器内加压热冲击国际比较评估研究概述(RPV PTS ICAS)

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This paper summarized the recently completed International Comparative Assessment Study of Pressurized Thermal-Shock in Reactor Pressure Vessels (RPV PTS ICAS). The ICAS project brought together international experts to perform comparative evaluations of methodologies employed in the assessment of RPV integrity under prototypical PTS conditions. ICAS grew out of a strong interest expressed by the participants to proceed with further evaluations after completion of the earlier FALSIRE II project. FALSIRE focused on evaluation of structural analysis and fracture assessment methods on the basis of experimental and analytical results. The ICAS problem statement defined transient thermal-mechanical conditions postulated to result from loss-of-coolant accidents in a Western type four-loop RPV with cladding on the inner surface. The primary focus was on the behavior of relatively shallow cracks located under and through the cladding. The assessment activities were divided into three tasks: Deterministic Fracture Mechanics (DFM), Probabilistic Fracture Mechanics (PFM) and Thermal-Hydraulic Mixing (THM). The results showed that a best-estimate methodology for RPV integrity assessment could benefit from a reduction of the uncertainties in each phase of the process. Within the DFM task, where account was taken of material properties and boundary conditions, reasonable agreement was obtained in linear-elastic and elastic-plastic analyses. Results from linear-elastic and J-estimation analyses were shown to provide conservative estimates of peak crack driving force when compared with those from complex 3D finite element analyses. For the PFM task, linear-elastic solutions were again shown to be conservative with respect to elastic-plastic solutions (by a factor of 2 to 4). Scatter in solutions obtained using the same computer code was generally attributable to differences in input parameters, e.g. standard deviations for the initial value of RT_(NDT), as well as for nickel and copper content. In the THM task, while there was a high degree of scatter during the early part of the transient, reasonable agreement was obtained during the latter part of the transient. Generally, the scatter was due to differences in analytical approaches used by the participants, which included correlation-based engineering methods, system codes and three-dimensional computational fluids dynamics codes. Based on concluding discussions from ICAS participants, a project is being organized to develop a computer software tool named QUAMET (acronym for QUAlification METhodology) for future use in qualifying codes and analysts engaged in the structural integrity assessment of RPVs.
机译:本文总结了最近完成的反应堆压力容器内加压热冲击的国际比较评估研究(RPV PTS ICAS)。 ICAS项目召集了国际专家,对在典型的PTS条件下评估RPV完整性所采用的方法进行了比较评估。 ICAS是出于参与者的强烈兴趣,在较早的FALSIRE II项目完成之后便进行了进一步的评估。 FALSIRE致力于根据实验和分析结果评估结构分析和断裂评估方法。 ICAS问题陈述定义了瞬态热机械条件,该瞬态热机械条件被认为是由内表面具有覆层的西方类型的四回路RPV中冷却剂损失事故引起的。主要关注于位于包层下方和穿过包层的较浅裂缝的行为。评估活动分为三个任务:确定性断裂力学(DFM),概率性断裂力学(PFM)和热液压混合(THM)。结果表明,用于RPV完整性评估的最佳估计方法可以受益于减少过程每个阶段的不确定性。在DFM任务中,考虑了材料特性和边界条件,在线性弹性和弹塑性分析中获得了合理的一致性。与复杂的3D有限元分析相比,线弹性和J估计分析的结果显示出峰值裂纹驱动力的保守估计。对于PFM任务,线弹性解决方案相对于弹塑性解决方案再次表现出保守性(2到4倍)。使用相同计算机代码获得的解决方案中的分散性通常可归因于输入参数(例如, RT_(NDT)的初始值以及镍和铜含量的标准偏差。在THM任务中,尽管在过渡的早期有很大程度的分散,但在过渡的后期获得了合理的同意。通常,分散是由于参与者使用的分析方法不同,其中包括基于相关的工程方法,系统代码和三维计算流体动力学代码。根据ICAS参与者的结论性讨论,正在组织一个项目,开发一个名为QUAMET(QUALification METhodology的缩写)的计算机软件工具,以供将来用于资格认证代码和RPV结构完整性评估的分析人员使用。

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