Effect of spray flow rate on pressure and temperature distribution in SMR containment

IF 2.1 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Nuclear Engineering and Design Pub Date : 2025-06-01 Epub Date: 2025-03-23 DOI:10.1016/j.nucengdes.2025.114005
Jinglin Cao, Xuefeng Lyu, Fenglei Niu, Jialei Chen
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Abstract

In the case of a direct vessel injection (DVI) line break in small modular reactors, the key to ensuring reactor safety is a timely and effective suppression of the pressure and temperature rise in the containment. In this paper, GASFLOW was utilized to analyze the influence of the internal spray mass flow rate on the pressure suppression and to compare 3D temperature distribution in the containment following the double-ended DVI line rupture. Results showed that the spray system significantly reduced the pressure and temperature in the containment in the initial phases. As the accident progressed, the impact of varying spray flow rates on the containment pressure and temperature gradually diminished, temperature distribution became more uniform, and the condensation effect of the spray ultimately stabilized. These findings substantiate the efficacy of the spray system and reveal a positive correlation between spray flow rates and more evident pressure suppression and cooling effects.
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喷雾流量对SMR安全壳压力和温度分布的影响
在小型模块化反应堆发生直接容器注入(DVI)断线的情况下,确保反应堆安全的关键是及时有效地抑制安全壳内的压力和温度上升。本文利用GASFLOW分析了内部喷雾质量流量对压力抑制的影响,对比了双端DVI管线破裂后容器内的三维温度分布。结果表明,喷雾系统在初始阶段显著降低了安全壳内的压力和温度。随着事故的进展,不同喷雾流量对安全壳压力和温度的影响逐渐减弱,温度分布趋于均匀,喷雾的冷凝效果最终趋于稳定。这些发现证实了喷雾系统的有效性,并揭示了喷雾流量与更明显的压力抑制和冷却效果之间的正相关关系。
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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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