花瓣形燃料组件通道内完全发育核沸腾特性的数值研究

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Lipeng Du , Tiezheng Wang , Qi Cheng , Xiang Chen , Wenchao Zhang , Jianchuang Sun , Weihua Cai
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引用次数: 0

摘要

完全发育成核沸腾(FDB)区分了单相流和两相流。FDB下游发生两相流。FDB对于过冷沸腾很重要。本文采用欧拉双流体模型和RPI壁面沸腾模型相结合的数值方法,对3 × 3花瓣形燃料组件通道内冷却剂流动沸腾的传热特性进行了数值研究,并对FDB特性进行了研究。如果汽泡直径超过离壁汽泡直径,则汽泡可以离壁,确定FDB。结果表明,加热功率对FDB的特性影响较小。随着进口过冷度的增大,FDB截面上主流温度降低,壁面过热度增大。随着进口质量流量的增大,FDB截面主流温度升高,壁面过热度增大。随着压力的增加,主流温度和壁面过热度的变化趋势与质量流量的增加一致。研究了现有预测相关性的适用性,结果表明Unal的FDB表达预测误差最小。为了减小误差,引入因子对预测表达式进行修正。与仿真结果比较,修正表达式的误差小于15%。内凹弧处壁面温度远高于外凸弧处壁面温度,内凹弧处冷却剂过冷沸腾强度明显。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Numerical investigation on characteristics of fully developed nucleate boiling (FDB) in petal-shape fuel assembly channel
Fully developed nucleate boiling (FDB) distinguishes between single-phase flow and two-phase flow. In downstream of FDB, two-phase flow occurs. FDB is important for subcooled boiling. In this paper, a numerical method combining the Eulerian two-fluid model and the RPI wall boiling model was adopted to numerically investigate the heat transfer characteristics of coolant flow boiling in a 3 × 3 petal-shaped fuel assembly channel and studied on the characteristics of FDB. If the diameter of vapor bubble exceed the departing bubble diameter, the bubble can depart from the wall, FDB is determined. The results showed that the heating power had a minor effect on the characteristic of FDB. As the inlet subcooling increased, the temperature of mainstream on the cross section of FDB decreased and wall superheat increased. As the inlet mass flow rate increased, the mainstream temperature on the section of FDB increased and the wall superheat increased. With the pressure increase, the change trend of mainstream temperature and wall superheat was the same as mass flow rate increased. Studied the suitability of existing prediction correlations, and the result showed that the error of Unal’s expression prediction of FDB was the minimum. To decrease the error, a factor was introduced to modify the prediction expression. Comparing with simulation result, the error of modified expression was less than 15 %. The wall temperature at the inner concave arc was much higher than that at the outer convex arc, and the intensity of the coolant subcooled boiling was sharply at the inner concave arc.
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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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