New correlation for Critical heat flux in annuli with low pressure water at low flow rates

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

Nuclear Engineering and Design Pub Date : 2025-04-14 DOI:10.1016/j.nucengdes.2025.114072

Mirza M. Shah

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Abstract

Calculation of CHF (Critical Heat Flux) for low pressure low flow water in annuli is required in the design and analyses of conventional nuclear reactors as well as the newer advanced nuclear reactors. Correlations for high pressure high flow have been found to fail for low pressure low flow conditions. There are no well-verified correlations under these conditions. The few published correlations have been verified with only a limited amount of data. In the present research, these correlations were compared to all available data which was from many sources. None of them was found satisfactory. A new correlation was therefore developed which agrees well with all available data for vertical annuli with upflow. The range of data included annular gaps 0.9 to 16.5 mm, pressures 1 to 3.2 bar, mass flux 1 to 1030 kg/m²s, and inlet quality −0.17 to 0. The new correlation had MAD (mean absolute deviation) of 19.6 % with 273 data points from 13 sources. The MAD of other correlations ranged from 45.3 % to 99.7 %. In this paper, previous work is reviewed, development of the new correlation is described, and comparison of the new and earlier correlations with test data is presented. Recommendations are made for its application.

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低流速低压水环流中临界热通量的新相关性

低压低流量环空水临界热流密度的计算是传统核反应堆设计和分析的需要，也是新型先进核反应堆设计和分析的需要。高压大流量的关系式在低压低流量条件下失效。在这些条件下没有得到充分证实的相关性。仅用有限数量的数据验证了少数已发表的相关性。在本研究中，将这些相关性与来自许多来源的所有可用数据进行了比较。没有一个令人满意。因此，建立了一个新的相关性，它与所有可用的垂直环空向上流动的数据吻合得很好。数据范围包括环空间隙0.9至16.5 mm，压力1至3.2 bar，质量通量1至1030 kg/m2s，进口质量- 0.17至0。新相关性的平均绝对偏差（MAD）为19.6%，来自13个来源的273个数据点。其他相关的MAD在45.3% ~ 99.7%之间。本文回顾了前人的工作，描述了新相关的发展，并将新的和早期的相关与试验数据进行了比较。对其应用提出了建议。

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.