Assessment of fluid-to-fluid similarity criteria to evaluate deterioration of heat transfer in flows of supercritical fluids

IF 2.5 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Nuclear Engineering and Design Pub Date : 2026-03-01 Epub Date: 2025-12-16 DOI:10.1016/j.nucengdes.2025.114683
Chukwudi Azih
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Abstract

In nuclear reactors, heat exchangers, and power cycles operating at supercritical thermodynamic conditions, heat transfer deterioration is a concern for the design and safety of primary heat removal components. Such deterioration can cause localized excursions in surface temperature, potentially compromising the integrity of the pressure boundary that contains the pressurized coolant. Therefore, accurately predicting flow conditions that lead to this deterioration is essential. To address this, numerous studies have investigated heat transfer at supercritical fluid states using various working fluids, including water. Building on previously published similarity criteria, this work evaluates deteriorated heat transfer predictive criteria against a more comprehensive dataset of over 480 tests. Unlike conventional approaches that normalize based on pressure at the critical state, the updated similarity criteria define surrogate fluid states using state-space similarity with peak Prandtl number, which arguably has more relevance to the flow. Additionally, dynamic flow criteria were examined by comparing the Richardson number with other buoyancy parameters and relevant ranges of Reynolds numbers were specified. The assessments were conducted for tubular geometries under upward flow, downward flow, and horizontal flow conditions. Particularly strong results are observed for the upward flow dataset, which comprises more than half of the database tests. Based on these evaluations, new predictive correlations for deteriorated heat transfer are proposed, applicable across broad ranges of Reynolds numbers and buoyancy parameters and fluids.
评价超临界流体流动中传热恶化的流体-流体相似性准则的评估
在核反应堆、热交换器和在超临界热力学条件下运行的动力循环中,传热恶化是主要排热部件的设计和安全所关注的问题。这种劣化会导致表面温度的局部偏移,潜在地损害包含加压冷却剂的压力边界的完整性。因此,准确预测导致这种恶化的流动条件至关重要。为了解决这个问题,许多研究使用各种工作流体(包括水)来研究超临界流体状态下的传热。在先前发布的相似标准的基础上,这项工作针对480多个测试的更全面的数据集评估了恶化的传热预测标准。与传统的基于临界状态压力的归一化方法不同,更新的相似性准则使用峰值普朗特数的状态空间相似性来定义替代流体状态,这可以说与流动更具相关性。此外,通过比较理查德森数与其他浮力参数来检验动态流动准则,并确定了相应的雷诺数范围。在向上流动、向下流动和水平流动条件下,对管状几何形状进行了评估。对于向上流数据集,可以观察到特别强的结果,它包含了超过一半的数据库测试。在这些评价的基础上,提出了新的变质传热预测相关性,适用于广泛的雷诺数、浮力参数和流体。
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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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