研究堆芯流动逆转现象的机理分析

IF 2.6 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Yuan Huang, Meng Lv, Heng Xie, Lei Shi
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引用次数: 0

摘要

提出了一种基于热压反馈的清华高通量堆堆芯强制循环失效后冷却剂回流过程的解析解。在这种情况下,冷却剂在核心内部产生的浮力的驱动下反向流动。系统分析了影响这一过程的关键因素。理论分析和计算流体力学(CFD)模拟均表明,回流所需时间主要受冷却剂通道宽度和冷却剂粘度的影响。最终的自然循环流速由冷却剂通道宽度、冷却剂粘度和反应堆功率水平决定。与核心固有的热-液压反馈相比,由余热排除系统提供的额外驱动头的响应速度更慢,幅度更小。在影响参数中,冷却剂通道宽度对最终流量和反转速度的影响最为显著。此外,燃料组件中未加热区域的存在略微降低了最终循环流速。在未来的反应堆设计中,必须严格控制燃料组件的加工和装配公差,并尽量减少应急泵的转动惯量,以促进堆芯内更快的回流。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Mechanism analysis of flow reversal phenomena in research reactor cores
An analytical solution for the coolant flow reversal process in the core of the Tsinghua High Flux Reactor (THFR) following the loss of forced circulation is developed based on thermal-hydraulic feedback. In this scenario, the coolant reverses direction driven by buoyancy forces generated within the core. Key factors influencing this process are systematically analyzed. Both theoretical analysis and computational fluid dynamics (CFD) simulations indicate that the time required for flow reversal is primarily influenced by the coolant channel width and coolant viscosity. The final natural circulation flow velocity is determined by the coolant channel width, coolant viscosity, and reactor power level. The additional driving head provided by the residual heat removal system responds more slowly and with lower magnitude compared to the core's inherent thermal-hydraulic feedback. Among the influencing parameters, the coolant channel width has the most significant impact on both the final flow rate and the reversal speed. Additionally, the presence of unheated regions in the fuel assemblies slightly reduces the final circulation flow rate. For future reactor designs, it is essential to tightly control the machining and assembly tolerances of fuel assemblies and minimize the rotational inertia of emergency pumps to facilitate faster flow reversal in the core.
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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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