Numerical analysis of a water-LBE interaction experiment: Sensitivity analysis, inverse uncertainty quantification and uncertainty propagation

IF 1.9 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Design Pub Date : 2025-04-08 DOI:10.1016/j.nucengdes.2025.114035

Qing Zhou, Xin’an Wang, Feng Mao

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引用次数: 0

Abstract

Accurately predicting reactor behavior during Steam Generator Tube Rupture (SGTR) events in Lead-Bismuth Cooled Fast Reactors (LBFRs) is critical for ensuring safety and reliability. This study employs a two-dimensional numerical simulation model to analyze water-LBE interactions during SGTR events with an experiment conducted at the China Nuclear Power Technology Research Institute (CNPRI). A comprehensive sensitivity analysis identified key input parameters that significantly influence pressure responses within the primary pool. Utilizing the Input Parameter Range Evaluation Methodology (IPREM), uncertainty ranges for these parameters were systematically determined. Monte Carlo method, guided by Wilks’ formula, propagated these uncertainties to generate uncertainty bands for pressure responses. The simulation results demonstrated that the uncertainty bands effectively encompassed the observed pressure transients, confirming the model’s reliability.

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水- lbe相互作用实验的数值分析：灵敏度分析、逆不确定性量化和不确定性传播

准确预测铅铋冷快堆（LBFRs）蒸汽发生管破裂（SGTR）事件时反应堆的行为对确保安全性和可靠性至关重要。本研究采用二维数值模拟模型，结合中国核电技术研究院（CNPRI）的实验，分析了SGTR事件中水- lbe的相互作用。综合敏感性分析确定了显著影响主油藏压力响应的关键输入参数。利用输入参数范围评估方法（IPREM），系统地确定了这些参数的不确定范围。蒙特卡罗方法在Wilks公式的指导下，传播这些不确定性，生成压力响应的不确定性带。仿真结果表明，不确定带有效地涵盖了实测压力瞬变，验证了模型的可靠性。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

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来源期刊

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.