卧式蒸汽发生器的几何形状与热水力结垢的关系

IF 2.1 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Milos A. Lazarevic, Vladimir D. Stevanovic, Sanja Milivojevic, Milan M. Petrovic
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引用次数: 0

摘要

大型核电站的成熟技术是小型模块化和中型反应堆发展的坚实基础。因此,研究几何形状与热水力结垢之间的关系,以利用大型电厂的优势开发安全可靠的小尺寸电厂具有重要意义。本研究调查了在wwer1000型核电站中建造的大型卧式蒸汽发生器(HSG)的热工液压系统,以及其复制品的热工液压系统,其几何形状缩小了50%。与大多数先前的研究主要依赖于相似概念进行标度分析不同,这项工作采用基于三维双流体模型方法和封闭定律的内部计算代码进行数值模拟,以预测界面输运现象。研究结果表明,在三维空间中,热液管道尺寸的均匀线性减小会导致热工参数的强烈非线性变化。如果50%缩小HSG的管束体积热流密度是全尺寸HSG的2倍,则全尺寸HSG和50%缩小HSG的管束体积热流密度沿竖直方向和水平方向的空隙率和两相流速度变化范围几乎相同。结果表明,在保持HSG一次和二次流体进出口温度和压力水平不变的情况下,减小管束直径和相应增加一次侧堆冷却剂流量可以显著增加体积热流密度。因此,按比例缩小的HSG结构可以显著提高单位管束体积的热功率,同时保持热水力条件的相似性,确保按比例缩小的HSG在与全尺寸HSG相当的安全可靠的范围内运行。这些发现有助于理解HSG结垢效应,并支持小型模块化和中型反应堆的开发。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Nexus between geometry and thermal-hydraulic scaling of horizontal steam generator
Mature technology of large-scale nuclear power plants is a strong basis for the development of small modular and medium size reactors. Therefore, it is important to study the nexus between geometry and thermal–hydraulic scaling with the aim to take advantage of large-scale plants to develop safe and reliable scaled-down plants. The present study investigates the thermal-hydraulics of a large-scale Horizontal Steam Generator (HSG) built in the WWER 1000 type nuclear power plant, and a thermal-hydraulics of its replica with the 50 % scaled-down geometry. Unlike most previous studies, which primarily relied on the similitude concept for scaling analysis, this work employs numerical simulations with an in-house computational code based on a three-dimensional two-fluid model approach and closure laws for the prediction of interfacial transport phenomena. Obtained results show that a uniform linear reduction of HSG dimensions in three-dimensional space leads to strong non-linear changes of thermal–hydraulic parameters. Nearly the same ranges of void fraction and two-phase flow velocity changes along vertical and horizontal directions of tube bundles are obtained in the full-size HSG and in the HSG with 50% scaled-down geometry if the tube bundle volumetric heat flux in the 50% scaled-down HSG geometry is two times greater than the full-size HSG value. It is shown that a significant increase of the volumetric heat flux is achievable with a reduced diameter of tubes in the bundle and a corresponding increase of the primary side reactor coolant flow rate, although the HSG primary and secondary fluid inlet and outlet temperatures and pressure levels are kept constant. Therefore, the scaled-down HSG geometry enables significant increase of heat power per unit of tube bundle volumes, while the preserved similarity of the thermal–hydraulic conditions ensures that the scaled-down HSG operates within safe and reliable limits comparable to the full-size HSG. The findings contribute to an understanding of HSG scaling effects and support the development of small modular and medium size reactors.
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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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