Enhancing computational efficiency of Bayesian Inference by identifying the intensity measure range to update seismic fragility curves

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Mrinal Jyoti Mahanta , Saran Srikanth Bodda , Abhinav Gupta , Jeong-Gon Ha
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引用次数: 0

Abstract

The United States Nuclear Regulatory Commission (US NRC) has established stringent criteria for the acceptance of new Standard Plant designs. These criteria require that the fragility curves have a high degree of confidence, especially in the low-probability regions. However, conventional methods of developing seismic fragility curves require a substantial number of dynamic analyses, which can be computationally intensive. To address this challenge, the Bayesian framework offers a more efficient and effective solution. Bayesian Inference enables the integration of prior knowledge with newly acquired data to refine the data-generating process. This manuscript presents a systematic Bayesian framework to update the seismic fragility curve of structures, systems, and components (SSCs). The efficiency of the framework is illustrated using an application to the seismic fragility of a concrete shear wall. Concrete Damage Plasticity Model (CDPM) is used to characterize the nonlinear behavior of concrete. The seismic fragility curve developed with our proposed approach aligns closely with those generated through conventional nonlinear simulations while significantly reducing the computational cost.
通过识别烈度测量范围来更新地震易损性曲线,提高贝叶斯推理的计算效率
美国核管理委员会(US NRC)为接受新的标准核电站设计制定了严格的标准。这些准则要求脆弱性曲线具有高度的置信度,特别是在低概率区域。然而,开发地震易损性曲线的常规方法需要进行大量的动态分析,这可能需要大量的计算。为了应对这一挑战,贝叶斯框架提供了一种更高效的解决方案。贝叶斯推理能够将先验知识与新获得的数据相结合,从而改进数据生成过程。本文提出了一个系统的贝叶斯框架来更新结构、系统和部件(ssc)的地震易损性曲线。通过混凝土剪力墙的地震易损性分析,说明了该框架的有效性。混凝土损伤塑性模型(CDPM)用于表征混凝土的非线性行为。用我们提出的方法开发的地震易损性曲线与通过传统非线性模拟生成的曲线非常接近,同时显著降低了计算成本。
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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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