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Seismic performance of degraded AGR cores

退化AGR岩心的抗震性能

基本信息

批准号：
1794075
负责人：
金额：
--
依托单位：
University of Bristol
依托单位国家：
英国
项目类别：
Studentship
财政年份：
2016
资助国家：
英国
起止时间：
2016 至无数据
项目状态：
已结题

来源：
https://gtr.ukri.org/projects?ref=studentship-1794075
关键词：
Seismic performance degraded AGR cores

项目摘要

This research is exploring the behaviour and contact dynamics of graphite cored nuclear reactors.The research will examine the correlation between experimental data and the analytical data. Thiswill lead to an identification of the useful questions that need to be answered in terms strengtheningthe safety case. The work will also look at how to improve the use of numerical tools to inform safetycase arguments. In particular it will compare existing experimental data with GCORE, SOLFEC,3DEC and other potential modelling approaches. This research will also aim to identify ways topredict the types of crack patterns that will lead to poorer dynamic performance of the array.Identifying these patterns could allow targeted core inspections focused on looking for the specifictypes of cracking that would be more critical to the overall core performance.Key outputs from the research:Further validation and verification of the numerical methodology, enhanced ways of interpreting thedata, deeper understanding of the fundamental mechanics of the aging core, identification of criticalcrack patterns.Timeline:Year 1: Study of data from tests to date and development of tools to aid comparison betweenexperimental and analytical results. Key deliverable - End of year report focussing on dataprocessing tools and initial findings from the research.Year 2: Identification of features that make particular crack cluster patterns more susceptible todamage in seismic events. Key deliverable - Report identifying types of patterns that could lead topoorer core performance.Year 3: Study of alternative core modelling techniques that could be used to better predict arraybehaviour under seismic loading. Key deliverable - Report identifying the limitations of the currentanalysis techniques and some ways that the analytical modelling can be improved.

本研究旨在探讨石墨芯核反应堆的行为和接触动力学，研究实验数据和分析数据之间的相关性。这将导致识别在加强安全情况方面需要回答的有用问题。这项工作还将着眼于如何改进数字工具的使用，以告知safetycase参数。特别是，它将比较现有的实验数据与GCORE，SOLFEC，3DEC和其他潜在的建模方法。本研究还旨在确定预测导致阵列动态性能变差的裂纹模式类型的方法。确定这些模式可以进行有针对性的堆芯检查，重点是寻找对堆芯整体性能更关键的特定类型的裂纹。研究的主要成果：进一步验证和验证数值方法，增强解释数据的方法，更深入地了解老化核心的基本力学，关键裂纹模式的识别。时间轴：第一年：研究迄今为止的试验数据，开发工具，以帮助比较实验和分析结果。关键交付成果--年底报告，重点是数据处理工具和研究的初步发现。第2年：识别使特定裂缝群模式在地震事件中更容易受到损害的特征。主要交付成果-确定可能导致地形仪核心性能的模式类型的报告。第3年：研究可用于更好地预测地震荷载下阵列行为的替代核心建模技术。关键交付品-报告查明当前分析技术的局限性以及改进分析建模的一些方法。