瞬态谱熵法检测自然循环沸水反应堆流动不稳定性

IF 2.1 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Nuclear Engineering and Design Pub Date : 2025-01-01 Epub Date: 2024-11-30 DOI:10.1016/j.nucengdes.2024.113675
Ch Santosh Subudhi, Sreyas Rajagopal Shimjith
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引用次数: 0

摘要

自然循环沸水堆(NCBWR)在一定的运行条件下,易发生冷却剂流动的热水力不稳定性。考虑到中子与热工水力学之间的强耦合,监测这些不稳定性对ncwr的安全可靠运行至关重要。然而,较宽的频率范围、显著的非平稳性和时变特性使得这一任务具有挑战性。本文介绍了一种利用瞬时谱熵(ISE)检测和评估流动不稳定性的新方法。该方法的主要优点是能够清楚地区分随机噪声和振荡。短时傅里叶变换(STFT)和连续小波变换(CWT)计算熵的比较表明,短时傅里叶变换(STFT)具有更好的计算效果。热工设施的运行数据验证了该方法在识别和评估时变流量不稳定性方面的有效性。
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Detection of flow instability in natural circulation boiling water reactors using instantaneous spectral entropy measure
Natural Circulation Boiling Water Reactors (NCBWR) are vulnerable to thermal-hydraulic instabilities in coolant flow under certain operating conditions. Considering the strong coupling between neutronics and thermal hydraulics, monitoring of such instabilities is crucial for safe and reliable operation of NCBWRs. However, wider frequency range, significant non-stationarity and time-varying nature of flow oscillations makes this a challenging task. In this paper, we introduce a novel method using Instantaneous Spectral Entropy (ISE) to detect and evaluate flow instabilities. Key advantage of the method is its ability to clearly differentiate between random noise and oscillations. Comparison between Short-Time Fourier Transform (STFT) and Continuous Wavelet Transform (CWT) for calculating entropy revealed that STFT provides superior results. Validation with operational data from a thermal hydraulic facility confirmed the method’s effectiveness in identifying and assessing time-varying flow instabilities.
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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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