核电站主蒸汽系统模型参数的多级灵敏度分析

IF 2.1 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Chenke Ding , Xiaoyu Luo , Sheng Zheng , Dazhi Zhang , Xian Zhang , Shanglong Huang , Yanda Zhu , Keming Ren , Junjie He
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引用次数: 0

摘要

核电站的主蒸汽系统是其热力系统的核心组成部分,为了确保效率和安全性,通常使用仿真模型对其运行进行监控。然而,系统模型的精度受到多个参数的不确定性的影响。在这种情况下,灵敏度分析是必不可少的,因为它识别了最关键的模型参数,从而减少了参数空间,提高了模型校准的效率和有效性。本文提出了一种结合Morris方法和广义似然不确定性估计(GLUE)方法的多级灵敏度分析框架。Morris方法作为一种有效的初步筛选技术,用于识别可能对模型输出产生重大影响的参数,从而有效地降低了参数空间的维数。随后,采用GLUE方法利用Nash-Sutcliffe效率系数评估模型对基准数据的拟合优度,得到模型参数的后验分布,量化参数的重要程度。结果表明,8个模型参数对模型输出有显著影响,为核电站主蒸汽系统的模型优化和参数调整提供了理论指导。该框架将计算时间从26.89 h减少到10.73 h,与传统方法相比,效率提高了60.1%,同时在关键模型参数识别方面保持了较高的准确性。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
A multi-level sensitivity analysis for the model parameters of the main steam system in nuclear power plants
The main steam system of a nuclear power plant is a core component of its thermal system, and its operation is typically monitored using simulation models to ensure both efficiency and safety. However, the accuracy of the system model is influenced by the uncertainty of multiple parameters. In this context, sensitivity analysis is essential, as it identifies the most key model parameters, thereby reducing the parameter space and enhancing the efficiency and effectiveness of model calibration. This paper presents a multi-level sensitivity analysis framework that combines the Morris method and the Generalized Likelihood Uncertainty Estimation (GLUE) method. The Morris method is employed as an efficient preliminary screening technique to identify parameters that potentially exert significant influence on model outputs, thereby effectively reducing the dimensionality of the parameter space. Subsequently, the GLUE method is applied to assess the model’s goodness-of-fit to benchmark data using the Nash–Sutcliffe efficiency coefficient, and the posterior distribution of model parameters is obtained to quantify the importance of the parameters. The results show that eight model parameters significantly affect the model output, providing theoretical guidance for model optimization and parameter adjustment of the nuclear power plant’s main steam system. The proposed framework reduces computational time from 26.89 h to 10.73 h, improving efficiency by 60.1% while maintaining high accuracy in key model parameter identification compared to traditional approaches.
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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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