Local and global sensitivity analyses on the overflow probability of Abadia de Goiás radioactive near surface repository

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
D.G. Teixeira , P.F. Frutuoso e Melo , L.G.M. Alvim , A.C.M. Alvim , A.S.M. Alves
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Abstract

This work presents a sensitivity analysis of the overflow probability of the near- surface radioactive repository built after the Abadia de Goiás accident, where radioactive 137Cs was released. The purpose of the analysis is to help the repository owner and the regulatory body make decisions on design parameters that affect the overflow probability. The following parameters have been considered: degradation function of the repository ceiling, internal porosity of the repository, internal area of the repository base, repository base and wall thicknesses, repository height, height of the liquid column inside the repository, average rainfall rate, evapotranspiration rate, surface runoff and hydraulic conductivity of the repository concrete. The choice for the range of each parameter is discussed. An investigation of the role of the mentioned parameters is detailed based on results obtained in a previous paper, and the dependencies among the rate parameters on the average rainfall rate is emphasized and modeled. To give a deeper perspective, local and global sensitivity analyses have been performed. In the case of global analysis, two approaches have been followed: in the first, the concept of Normalized Mutual Information and the other one leverages Shapley values derived from Light Gradient Boosting Machine and Shapley values have been used for investigating non-linearities. For some parameters the lowest values are to be considered, e.g., the repository base thickness and the average rainfall rate, while for others the highest value is desirable, like the evapotranspiration rate and the surface runoff in order to obtain lower overflow probabilities. These results should be looked with care because nonlinearities have been identified by the Shapley value analysis. Overall, the degradation function and the evapotranspiration rate emerge as the most influential parameters. The legacy of this work lies in the robust methodological framework it provides, paving the way for enhanced safety assessments and improved design practices in complex environmental systems.
Abadia de Goiás放射性近地表储存库溢流概率的局部和全局敏感性分析
本文对Abadia de Goiás事故后建造的近地表放射性储存库溢出概率进行了敏感性分析,该事故释放了放射性137Cs。分析的目的是帮助存储库所有者和管理机构对影响溢出概率的设计参数做出决策。考虑了以下参数:库顶的退化函数、库内部孔隙率、库基座的内部面积、库基座和壁厚、库高度、库内液柱高度、平均降雨率、蒸散发率、地表径流和库混凝土的水力导率。讨论了各参数取值范围的选择。在前人研究的基础上,详细探讨了上述参数的作用,并着重讨论了速率参数对平均降雨量的依赖关系,并建立了模型。为了提供更深入的观点,进行了局部和全球敏感性分析。在全局分析的情况下,遵循了两种方法:第一种方法是标准化互信息的概念,另一种方法是利用从光梯度增强机导出的Shapley值和Shapley值来研究非线性。对于某些参数,应考虑最低值,例如库底厚度和平均降雨率,而对于其他参数,则应考虑最高值,例如蒸散速率和地表径流,以获得较低的溢出概率。这些结果应该仔细观察,因为非线性已经由沙普利值分析确定。总体而言,退化函数和蒸散发速率是影响最大的参数。这项工作的遗产在于它提供了强大的方法框架,为加强安全评估和改进复杂环境系统中的设计实践铺平了道路。
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来源期刊
Nuclear Engineering and Design
Nuclear Engineering and Design 工程技术-核科学技术
CiteScore
3.40
自引率
11.80%
发文量
377
审稿时长
5 months
期刊介绍: Nuclear Engineering and Design covers the wide range of disciplines involved in the engineering, design, safety and construction of nuclear fission reactors. The Editors welcome papers both on applied and innovative aspects and developments in nuclear science and technology. Fundamentals of Reactor Design include: • Thermal-Hydraulics and Core Physics • Safety Analysis, Risk Assessment (PSA) • Structural and Mechanical Engineering • Materials Science • Fuel Behavior and Design • Structural Plant Design • Engineering of Reactor Components • Experiments Aspects beyond fundamentals of Reactor Design covered: • Accident Mitigation Measures • Reactor Control Systems • Licensing Issues • Safeguard Engineering • Economy of Plants • Reprocessing / Waste Disposal • Applications of Nuclear Energy • Maintenance • Decommissioning Papers on new reactor ideas and developments (Generation IV reactors) such as inherently safe modular HTRs, High Performance LWRs/HWRs and LMFBs/GFR will be considered; Actinide Burners, Accelerator Driven Systems, Energy Amplifiers and other special designs of power and research reactors and their applications are also encouraged.
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