螺旋卷绕蒸汽发生器流动不稳定性的计算和实验研究

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Annals of Nuclear Energy Pub Date : 2024-08-21 DOI:10.1016/j.anucene.2024.110834
{"title":"螺旋卷绕蒸汽发生器流动不稳定性的计算和实验研究","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":"{\"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}","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

摘要

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。
查看原文
分享 分享
微信好友 朋友圈 QQ好友 复制链接
本刊更多论文
Calculation and experimental study on the flow instability behavior of a helically coiled steam generator

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.

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
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.
期刊最新文献
Layered target design method for global spectrum optimization of radioisotope production Experimental study on the plate-type fuel melting behavior based on alternative materials Griffin: A MOOSE-based reactor physics application for multiphysics simulation of advanced nuclear reactors Research on the high-performance computing method for the neutron diffusion spatiotemporal kinetics equation based on the convolutional neural network Steady-state thermal–hydraulic analysis of an NTP reactor core based on the porous medium approach
×
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
现在去查看 取消
×
提示
确定
0
微信
客服QQ
Book学术公众号 扫码关注我们
反馈
×
意见反馈
请填写您的意见或建议
请填写您的手机或邮箱
已复制链接
已复制链接
快去分享给好友吧!
我知道了
×
扫码分享
扫码分享
Book学术官方微信
Book学术文献互助
Book学术文献互助群
群 号:481959085
Book学术
文献互助 智能选刊 最新文献 互助须知 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 Book学术 All rights reserved.
ghs 京公网安备 11010802042870号 京ICP备2023020795号-1