Numerical appraisal of the role of heat transfer regimes on transient response of carbon dioxide based supercritical natural circulation loop during power upsurge

IF 2.1 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Nuclear Engineering and Design Pub Date : 2024-12-01 Epub Date: 2024-09-21 DOI:10.1016/j.nucengdes.2024.113601
Tanuj Srivastava , Ashok Kumar Gond , Dipankar N. Basu
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Abstract

Appearance of steep property gradients with change in temperature is a fascinating feature of any supercritical fluid, which can instigate intricate dynamics in supercritical natural circulation loops by modulating the effective forces. While most of the relevant literature focuses on stability evaluation, anticipation regarding the transient response of the system during power transition is of utmost significance, especially in high-power applications. Present study aims at furnishing insight on the same by developing a one-dimensional numerical model of a rectangular loop with supercritical CO2 as the working medium, and characterizing the temporal trends over a wide range of heating power. Two different profiles of power upsurge have been tested for different regimes of heat transfer, unearthing intriguing characteristics. The combination of initial and final regimes during any transformation is found to be the most crucial factor. Single-step rise in power, in general, is the most vulnerable one, specifically during large-scale change of the order of 1000 W, and better be employed only at low-power regime. Even single-step change 25 W can inflict instability and flow transition within the transition regime. Power transformation following linear ramp profile with transition periods of 5, 10 and 20 s is identified to be the most suitable one across all the regimes. It can successfully mitigate instability even in the later parts of the transition regime, albeit at the expense of greater time requirement to attain the final stable state and possibly a greater period of transformation. Change through multiple small steps (about 250 W for large change in low power regime and 15 W within transition regime) can also be a feasible option for avoiding the growth of unstable oscillations at higher powers.
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基于二氧化碳的超临界自然循环回路在电力高峰期的瞬态响应中传热机制作用的数值评估
随着温度的变化出现陡峭的性质梯度是任何超临界流体的一个迷人特征,它可以通过调节有效作用力在超临界自然循环环路中产生复杂的动态变化。虽然大多数相关文献都侧重于稳定性评估,但对系统在功率转换期间的瞬态响应进行预测却至关重要,尤其是在大功率应用中。本研究旨在通过建立以超临界二氧化碳为工作介质的矩形环路的一维数值模型,并描述在宽泛的加热功率范围内的时间变化趋势,来深入探讨这一问题。针对不同的传热状态,测试了两种不同的功率上升曲线,发现了一些有趣的特征。我们发现,在任何转变过程中,初始和最终状态的结合是最关键的因素。一般来说,功率的单步上升是最脆弱的,特别是在 1000 W 的大规模变化时,最好只在低功率状态下使用。即使是 25 W 的单级变化也会造成不稳定,并在过渡状态下产生流动转换。按照线性斜坡曲线进行功率变换,过渡时间分别为 5 秒、10 秒和 20 秒,在所有情况下都是最合适的。尽管达到最终稳定状态所需的时间更长,转换周期也可能更长,但它仍能成功地缓解不稳定性,甚至在过渡状态的后期也是如此。通过多个小步骤进行变化(低功率状态下的大变化约为 250 瓦,过渡状态下为 15 瓦)也是一种可行的选择,可避免在较高功率下出现不稳定振荡。
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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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