An adaptive three-dimensional model for thermal hydraulics analysis of a PWR steam generator

IF 2.3 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Yung Suk Nam , Han Young Yoon
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引用次数: 0

Abstract

Pressurized Water Reactor (PWR) steam generators (SGs) feature complex internal structures, including numerous heat exchanger tubes and support components. Accurate modeling of these internal structures is essential for reliable thermal–hydraulic analysis. However, conventional modeling approaches for SG thermal hydraulic analysis often require significant effort and time, limiting efficiency and flexibility. In this paper, we propose an adaptive three-dimensional (3D) modeling approach for the internal structures of PWR SGs, enabling comprehensive and efficient thermal–hydraulic analysis applicable to various designs. The 3D mesh encompasses all critical regions of the SG, including the U-tube heat exchanger, riser, downcomer, and steam dome. A dedicated mesh model accurately representing the shape of the U-tube bundle was developed, with the total tube length calculated from the model differing by less than 1% compared to design specifications. The CUPID-SG code (CUPID for SG application), based on the two-fluid model, is employed to perform the thermal–hydraulic analysis using the proposed 3D mesh. CUPID-SG incorporates primary coolant, U-tube heat conduction, and secondary coolant two-phase flow models, providing a comprehensive framework for simulation. The effectiveness of the proposed approach is demonstrated through the thermal–hydraulic analysis of the APR1400 SG, validating its capability for accurate and adaptable modeling of PWR SGs.
一种用于压水堆蒸汽发生器热水力分析的自适应三维模型
压水堆(PWR)蒸汽发生器(SGs)具有复杂的内部结构,包括许多热交换器管和支撑部件。这些内部结构的精确建模对于可靠的热水力分析至关重要。然而,SG热水力分析的传统建模方法通常需要大量的精力和时间,限制了效率和灵活性。在本文中,我们提出了一种自适应的三维(3D)建模方法,以实现适用于各种设计的全面、高效的热工分析。三维网格覆盖了SG的所有关键区域,包括u型管换热器、立管、下水管和蒸汽穹顶。开发了一个精确表示u型管束形状的专用网格模型,与设计规格相比,该模型计算的总管长差异小于1%。采用基于双流体模型的丘比特-SG代码(丘比特为SG应用),对所提出的三维网格进行热液分析。CUPID-SG集成了一次冷却剂、u型管热传导和二次冷却剂两相流模型,为模拟提供了全面的框架。通过对APR1400 SG的热水力分析验证了该方法的有效性,验证了该方法对压水堆SG进行精确、适应性建模的能力。
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来源期刊
Annals of Nuclear Energy
Annals of Nuclear Energy 工程技术-核科学技术
CiteScore
4.30
自引率
21.10%
发文量
632
审稿时长
7.3 months
期刊介绍: Annals of Nuclear Energy provides an international medium for the communication of original research, ideas and developments in all areas of the field of nuclear energy science and technology. Its scope embraces nuclear fuel reserves, fuel cycles and cost, materials, processing, system and component technology (fission only), design and optimization, direct conversion of nuclear energy sources, environmental control, reactor physics, heat transfer and fluid dynamics, structural analysis, fuel management, future developments, nuclear fuel and safety, nuclear aerosol, neutron physics, computer technology (both software and hardware), risk assessment, radioactive waste disposal and reactor thermal hydraulics. Papers submitted to Annals need to demonstrate a clear link to nuclear power generation/nuclear engineering. Papers which deal with pure nuclear physics, pure health physics, imaging, or attenuation and shielding properties of concretes and various geological materials are not within the scope of the journal. Also, papers that deal with policy or economics are not within the scope of the journal.
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