钠冷快堆原型蒸汽发生器的精细化数值分析

IF 2.3 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Bo Wang, Yan Zhang, Yang Yang, Zhengrong Guo, Jun Fan, Mingyang Li
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引用次数: 0

摘要

本文对钠冷快堆蒸汽发生器原型进行了全面的三维数值模拟。该模型的特点是钠侧以1:1的几何表示形式进行详细的网格划分,而水侧则利用用户自定义功能进行精确的热建模。模拟综合了钠水蒸汽发生器两侧的耦合流动和传热过程。对实验数据的验证证实了模型的可靠性,在额定功率和28%功率条件下,钠的温度和热负荷分布都表现出较好的一致性。该研究揭示了详细的流动和传热特性,包括钠侧流场、压力场和温度场,以及水侧流体和壁面温度和传热系数。结果表明,管束大部分区域的热负荷分布相对均匀。为钠冷快堆蒸汽发生器的设计优化、性能改进和安全性评价提供了坚实的理论基础和有效的技术支持。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Refined numerical analysis of prototype steam generator for sodium-cooled fast reactor
This paper presents a comprehensive three-dimensional numerical simulation of a prototype steam generator for a sodium-cooled fast reactor. The model features a 1:1 geometric representation of the sodium side with detailed meshing, while the water side utilizes a User-Defined Function for accurate thermal modeling. The simulation integrates the coupled flow and heat transfer processes on both sides of the sodium-water steam generator. Validation against experimental data confirms the model’s reliability, showing good agreement in sodium temperature and heat load distribution under both rated and 28% power conditions. The study reveals detailed flow and heat transfer characteristics, including sodium-side flow fields, pressure fields, and temperature fields, as well as water-side fluid and wall temperatures and heat transfer coefficients. Results indicate a relatively uniform heat load distribution in most areas of the tube bundle. This work provides a robust theoretical foundation and effective technical support for the design optimization, performance improvement, and safety assessment of sodium-cooled fast reactor steam generators.
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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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