下置式捕集器自然循环冷却系统的实验研究

IF 2.6 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Seokgyu Jeong, Byeonghee Lee, Jun-young Kang, Seong Ho Hong, Chang Wan Kang, Jin Hyeok Kim
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引用次数: 0

摘要

堆芯捕集器是用于防止核电站安全壳失效的严重事故缓解装置。在韩国,部分出口型核反应堆采用了PECS(被动容器外堆芯保留和冷却系统)堆芯捕集器设计。本研究利用VPEX(可变PECS实验设施)研究了这一概念设计的核心捕集器PECS的冷却性能。结果表明,平均热流密度为232 kW/m2,是预测热流密度的1.75倍,制冷效果良好。此外,还分析了大型下向加热通道的水力和传热特性。结果表明,与普通实验室规模的设备相比,大型设备的传热系数值相对较低。较低的进口压力和较少的过冷提高了自然循环质量流量和空隙率。进口压力、过冷度或热流密度的变化对表面传热特性(如沸腾曲线或传热系数)的影响最小。基于这些实验结果,开发了NCir(自然循环计算器)分析代码。Wallis模型为孔隙率和自然循环质量流量的计算提供了最准确的预测。实验结果和预测代码在未来的PECS分析中具有潜在的应用价值。此外,它们还可以作为具有类似VPEX的向下加热结构的大型设施的基础数据。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Experimental study on natural circulation cooling system for core catcher with downward-facing heating channel
Core catchers are severe accident mitigation devices designed to prevent containment failure in nuclear power plants. In Korea, certain export-oriented nuclear reactors have adopted the PECS (Passive Ex-vessel corium retaining and Cooling System) core catcher design. This study investigates the cooling performance of this conceptually designed core catcher, PECS, using a scaled experimental facility, VPEX (Variable PECS EXperimental facility). The results showed that the cooling performance was satisfactory at an average heat flux value of 232 kW/m2, which is 1.75 times higher than predicted heat flux value. Furthermore, hydraulic and heat transfer characteristics for large-scale downward-facing heating channels were analyzed. It was observed that the large-scale facility exhibited relatively low heat transfer coefficient values compared to common laboratory scale facilities. Lower inlet pressures and less subcooling enhanced natural circulation mass flow rates and void fractions. Variations in inlet pressure, subcooling, or heat flux had minimal impacts on surface heat transfer characteristics such as boiling curves or heat transfer coefficients. Based on these experimental findings, the NCir (Natural Circulation calculator) analysis code was developed. The Wallis model provided the most accurate predictions for void fraction and natural circulation mass flow rate calculations. The experimental results and prediction code have potential applications in future PECS analyses. Additionally, they serve as fundamental data for large-scale facilities with downward-facing heating structures similar to VPEX.
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来源期刊
Nuclear Engineering and Technology
Nuclear Engineering and Technology 工程技术-核科学技术
CiteScore
4.80
自引率
7.40%
发文量
431
审稿时长
3.5 months
期刊介绍: Nuclear Engineering and Technology (NET), an international journal of the Korean Nuclear Society (KNS), publishes peer-reviewed papers on original research, ideas and developments in all areas of the field of nuclear science and technology. NET bimonthly publishes original articles, reviews, and technical notes. The journal is listed in the Science Citation Index Expanded (SCIE) of Thomson Reuters. NET covers all fields for peaceful utilization of nuclear energy and radiation as follows: 1) Reactor Physics 2) Thermal Hydraulics 3) Nuclear Safety 4) Nuclear I&C 5) Nuclear Physics, Fusion, and Laser Technology 6) Nuclear Fuel Cycle and Radioactive Waste Management 7) Nuclear Fuel and Reactor Materials 8) Radiation Application 9) Radiation Protection 10) Nuclear Structural Analysis and Plant Management & Maintenance 11) Nuclear Policy, Economics, and Human Resource Development
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