Calculation and experimental study on the flow instability behavior of a helically coiled steam generator

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
{"title":"Calculation and experimental study on the flow instability behavior of a helically coiled steam generator","authors":"","doi":"10.1016/j.anucene.2024.110834","DOIUrl":null,"url":null,"abstract":"<div><p>The flow instability phenomenon in the helically coiled steam generator may cause continuous large oscillations in flow rate and wall temperature. An experimental and calculation study was carried out to investigate the flow instability behavior of a helically coiled heat exchanger. The flow instability threshold with thermal power within 0.6 MW–2.3 MW is obtained. The increase of inlet throttling and thermal power stabilize the system. Both of the tube-side and shell-side parameters, such as flow rate, temperature, and pressure affect the flow instability thresholds. In addition, the SGTH-1D code is used to simulate the flow instability threshold of the heat exchanger. The SGTH-1D code can accurately estimate the flow instability threshold of the heat exchanger. Finally, a new 3D flow instability map is proposed using the phase change number, the modified subcooled number and the inlet throttling number to estimate the flow instability threshold in the heat exchanger.</p></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":null,"pages":null},"PeriodicalIF":1.9000,"publicationDate":"2024-08-21","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Annals of Nuclear Energy","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0306454924004973","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

Abstract

The flow instability phenomenon in the helically coiled steam generator may cause continuous large oscillations in flow rate and wall temperature. An experimental and calculation study was carried out to investigate the flow instability behavior of a helically coiled heat exchanger. The flow instability threshold with thermal power within 0.6 MW–2.3 MW is obtained. The increase of inlet throttling and thermal power stabilize the system. Both of the tube-side and shell-side parameters, such as flow rate, temperature, and pressure affect the flow instability thresholds. In addition, the SGTH-1D code is used to simulate the flow instability threshold of the heat exchanger. The SGTH-1D code can accurately estimate the flow instability threshold of the heat exchanger. Finally, a new 3D flow instability map is proposed using the phase change number, the modified subcooled number and the inlet throttling number to estimate the flow instability threshold in the heat exchanger.

螺旋卷绕蒸汽发生器流动不稳定性的计算和实验研究
螺旋盘管蒸汽发生器中的流动不稳定现象可能会导致流量和壁温持续大幅波动。我们通过实验和计算研究了螺旋盘管换热器的流动不稳定性。得出了热功率在 0.6 MW-2.3 MW 范围内的流动不稳定性阈值。入口节流和热功率的增加使系统趋于稳定。流量、温度和压力等管侧和壳侧参数都会影响流动不稳定阈值。此外,SGTH-1D 代码还用于模拟热交换器的流动不稳定阈值。SGTH-1D 代码可以准确估计热交换器的流动不稳定性阈值。最后,利用相变数、修正过冷度数和入口节流数提出了一种新的三维流动不稳定图,用于估算热交换器中的流动不稳定阈值。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
求助全文
约1分钟内获得全文 求助全文
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.
×
引用
GB/T 7714-2015
复制
MLA
复制
APA
复制
导出至
BibTeX EndNote RefMan NoteFirst NoteExpress
×
提示
您的信息不完整,为了账户安全,请先补充。
现在去补充
×
提示
您因"违规操作"
具体请查看互助需知
我知道了
×
提示
确定
请完成安全验证×
copy
已复制链接
快去分享给好友吧!
我知道了
右上角分享
点击右上角分享
0
联系我们:info@booksci.cn Book学术提供免费学术资源搜索服务,方便国内外学者检索中英文文献。致力于提供最便捷和优质的服务体验。 Copyright © 2023 布克学术 All rights reserved.
京ICP备2023020795号-1
ghs 京公网安备 11010802042870号
Book学术文献互助
Book学术文献互助群
群 号:481959085
Book学术官方微信