分离式管壳式蒸汽发生器在不同工况下的热工性能研究

IF 2.1 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Design Pub Date : 2025-10-07 DOI:10.1016/j.nucengdes.2025.114505

Huaishuang Shao, Jiang Chang, Jian Jiao, Zhiyuan Liang, Yungang Wang, Qinxin Zhao

{"title":"分离式管壳式蒸汽发生器在不同工况下的热工性能研究","authors":"Huaishuang Shao, Jiang Chang, Jian Jiao, Zhiyuan Liang, Yungang Wang, Qinxin Zhao","doi":"10.1016/j.nucengdes.2025.114505","DOIUrl":null,"url":null,"abstract":"<div><div>A thermal–hydraulic performance analysis program based on Fluent was developed for separated structure shell-and-tube steam generator. The coupled heat transfer on both sides of the steam generator and the anisotropic flow resistance model of the vapor–liquid two-phase flow across tube bundle were mainly considered. The reliability of the program has been verified by experimental data. Based on the program, the effects of different inlet flue gas temperatures, flue gas mass flow rates and operating pressures on the thermal–hydraulic characteristics were studied. It was found that flue gas temperature and flue gas flow rate mainly affect the heat flux distribution. With the increase of flue gas temperature and flow rate, the vapor void fraction and flow velocity on the shell side increase accordingly. The flow resistance inside the shell and the local resistance at the inlet of the riser increase accordingly, but the overall natural circulation flow rate still increased by 38.72% and 13.19% respectively. It showed a positive compensation characteristic with head load. The operating pressure mainly affects the physical property of the working fluid. The lower the pressure, the higher the vapor void fraction on the shell side. Although the flow resistance inside the shell increased under low pressure condition, the overall natural circulation flow rate still increased by 42.33% due to larger circulation pressure difference. This can provide a reference for the structural design of the separated structure shell-and-tube steam generator.</div></div>","PeriodicalId":19170,"journal":{"name":"Nuclear Engineering and Design","volume":"445 ","pages":"Article 114505"},"PeriodicalIF":2.1000,"publicationDate":"2025-10-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"Study on the thermal hydraulic performance of a separated structure shell-and-tube steam generator under various operating conditions\",\"authors\":\"Huaishuang Shao, Jiang Chang, Jian Jiao, Zhiyuan Liang, Yungang Wang, Qinxin Zhao\",\"doi\":\"10.1016/j.nucengdes.2025.114505\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><div>A thermal–hydraulic performance analysis program based on Fluent was developed for separated structure shell-and-tube steam generator. The coupled heat transfer on both sides of the steam generator and the anisotropic flow resistance model of the vapor–liquid two-phase flow across tube bundle were mainly considered. The reliability of the program has been verified by experimental data. Based on the program, the effects of different inlet flue gas temperatures, flue gas mass flow rates and operating pressures on the thermal–hydraulic characteristics were studied. It was found that flue gas temperature and flue gas flow rate mainly affect the heat flux distribution. With the increase of flue gas temperature and flow rate, the vapor void fraction and flow velocity on the shell side increase accordingly. The flow resistance inside the shell and the local resistance at the inlet of the riser increase accordingly, but the overall natural circulation flow rate still increased by 38.72% and 13.19% respectively. It showed a positive compensation characteristic with head load. The operating pressure mainly affects the physical property of the working fluid. The lower the pressure, the higher the vapor void fraction on the shell side. Although the flow resistance inside the shell increased under low pressure condition, the overall natural circulation flow rate still increased by 42.33% due to larger circulation pressure difference. This can provide a reference for the structural design of the separated structure shell-and-tube steam generator.</div></div>\",\"PeriodicalId\":19170,\"journal\":{\"name\":\"Nuclear Engineering and Design\",\"volume\":\"445 \",\"pages\":\"Article 114505\"},\"PeriodicalIF\":2.1000,\"publicationDate\":\"2025-10-07\",\"publicationTypes\":\"Journal Article\",\"fieldsOfStudy\":null,\"isOpenAccess\":false,\"openAccessPdf\":\"\",\"citationCount\":\"0\",\"resultStr\":null,\"platform\":\"Semanticscholar\",\"paperid\":null,\"PeriodicalName\":\"Nuclear Engineering and Design\",\"FirstCategoryId\":\"5\",\"ListUrlMain\":\"https://www.sciencedirect.com/science/article/pii/S002954932500682X\",\"RegionNum\":3,\"RegionCategory\":\"工程技术\",\"ArticlePicture\":[],\"TitleCN\":null,\"AbstractTextCN\":null,\"PMCID\":null,\"EPubDate\":\"\",\"PubModel\":\"\",\"JCR\":\"Q1\",\"JCRName\":\"NUCLEAR SCIENCE & TECHNOLOGY\",\"Score\":null,\"Total\":0}","platform":"Semanticscholar","paperid":null,"PeriodicalName":"Nuclear Engineering and Design","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S002954932500682X","RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q1","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}

引用次数: 0

摘要

基于Fluent开发了分离式管壳式蒸汽发生器的热工性能分析程序。主要考虑了蒸汽发生器两侧的耦合换热和汽液两相流跨管束的各向异性流动阻力模型。实验数据验证了程序的可靠性。在此基础上，研究了不同进口烟气温度、烟气质量流量和操作压力对热工特性的影响。研究发现，烟气温度和烟气流量是影响热流密度分布的主要因素。随着烟气温度和流量的升高，壳侧的汽蚀率和流速也相应增大。壳内流动阻力和立管进口局部阻力相应增大，但总体自然循环流量仍分别增大38.72%和13.19%。对水头负荷表现出正补偿特性。操作压力主要影响工作流体的物理性质。压力越低，壳侧的蒸气空隙率越高。低压工况下，虽然壳内流动阻力增大，但由于循环压差较大，总体自然循环流量仍增加了42.33%。这可为分离式壳管式蒸汽发生器的结构设计提供参考。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

查看原文本刊更多论文

Study on the thermal hydraulic performance of a separated structure shell-and-tube steam generator under various operating conditions

A thermal–hydraulic performance analysis program based on Fluent was developed for separated structure shell-and-tube steam generator. The coupled heat transfer on both sides of the steam generator and the anisotropic flow resistance model of the vapor–liquid two-phase flow across tube bundle were mainly considered. The reliability of the program has been verified by experimental data. Based on the program, the effects of different inlet flue gas temperatures, flue gas mass flow rates and operating pressures on the thermal–hydraulic characteristics were studied. It was found that flue gas temperature and flue gas flow rate mainly affect the heat flux distribution. With the increase of flue gas temperature and flow rate, the vapor void fraction and flow velocity on the shell side increase accordingly. The flow resistance inside the shell and the local resistance at the inlet of the riser increase accordingly, but the overall natural circulation flow rate still increased by 38.72% and 13.19% respectively. It showed a positive compensation characteristic with head load. The operating pressure mainly affects the physical property of the working fluid. The lower the pressure, the higher the vapor void fraction on the shell side. Although the flow resistance inside the shell increased under low pressure condition, the overall natural circulation flow rate still increased by 42.33% due to larger circulation pressure difference. This can provide a reference for the structural design of the separated structure shell-and-tube steam generator.

求助全文

通过发布文献求助，成功后即可免费获取论文全文。去求助

来源期刊

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.