Flow oscillation fade-out and pool water level effect experiments on open loop passive cooling system

IF 2.1 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Nuclear Engineering and Design Pub Date : 2025-08-01 Epub Date: 2025-04-25 DOI:10.1016/j.nucengdes.2025.114087
Joonas Telkkä, Vesa Riikonen, Antti Räsänen, Eetu Kotro, Juhani Hyvärinen
{"title":"Flow oscillation fade-out and pool water level effect experiments on open loop passive cooling system","authors":"Joonas Telkkä,&nbsp;Vesa Riikonen,&nbsp;Antti Räsänen,&nbsp;Eetu Kotro,&nbsp;Juhani Hyvärinen","doi":"10.1016/j.nucengdes.2025.114087","DOIUrl":null,"url":null,"abstract":"<div><div>The stable operating conditions for an open loop passive containment heat removal system were identified through testing conducted with the PASI test facility, a half-height wall condenser model at LUT University, Finland. Previous tests have shown that open loop systems tend to operate in a quasi-steady oscillatory mode characterized by geysering and flashing. The cessation of flow oscillations depends on the sparger structure. When flooding of the riser pipeline is prevented, the oscillation fade-out and steady two-phase natural circulation is reached quickly after the system reaches saturation conditions. Conversely, if flooding is allowed, the oscillations disappear only at heating power large enough to meet the countercurrent flow limitation (CCFL) criterion in the riser. The impact of gravity head on the system behavior was also examined. The amplitude of two-phase flow oscillations decreased along the lowering of the pool water level. When the water level decreased below the pressure balancing hole, the flow behavior changed since the riser flooding ended. Additionally, the riser boil-out was tested. The results show that the open-loop natural circulation system can effectively remove heat as long as there is water inventory inside the loop, even if the pool is empty of water. The containment pressure rises only when boiling initiates in the heat exchanger.</div></div>","PeriodicalId":19170,"journal":{"name":"Nuclear Engineering and Design","volume":"439 ","pages":"Article 114087"},"PeriodicalIF":2.1000,"publicationDate":"2025-08-01","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/S002954932500264X","RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"2025/4/25 0:00:00","PubModel":"Epub","JCR":"Q1","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}
引用次数: 0

Abstract

The stable operating conditions for an open loop passive containment heat removal system were identified through testing conducted with the PASI test facility, a half-height wall condenser model at LUT University, Finland. Previous tests have shown that open loop systems tend to operate in a quasi-steady oscillatory mode characterized by geysering and flashing. The cessation of flow oscillations depends on the sparger structure. When flooding of the riser pipeline is prevented, the oscillation fade-out and steady two-phase natural circulation is reached quickly after the system reaches saturation conditions. Conversely, if flooding is allowed, the oscillations disappear only at heating power large enough to meet the countercurrent flow limitation (CCFL) criterion in the riser. The impact of gravity head on the system behavior was also examined. The amplitude of two-phase flow oscillations decreased along the lowering of the pool water level. When the water level decreased below the pressure balancing hole, the flow behavior changed since the riser flooding ended. Additionally, the riser boil-out was tested. The results show that the open-loop natural circulation system can effectively remove heat as long as there is water inventory inside the loop, even if the pool is empty of water. The containment pressure rises only when boiling initiates in the heat exchanger.
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
开环被动冷却系统流动振荡淡出及池水位效应试验
通过芬兰LUT大学的半高壁式冷凝器模型PASI测试设施进行的测试,确定了开环被动容器排热系统的稳定运行条件。先前的测试表明,开环系统倾向于以间歇泉和闪烁为特征的准稳定振荡模式运行。流动振荡的停止取决于分散器的结构。防止隔水管淹水后,系统达到饱和状态后,振荡逐渐消失,迅速达到稳定的两相自然循环。相反,如果允许溢流,只有在加热功率大到足以满足立管逆流限制(CCFL)标准时,振荡才会消失。研究了重力头对系统性能的影响。两相流振荡幅值随池水位的降低而减小。当水位下降到压力平衡孔以下时,隔水管注水结束后,流动特性发生变化。此外,还测试了立管沸出。结果表明,开环自然循环系统可以有效地去除热量,只要循环内有水库存,即使池中的水是空的。只有当热交换器中开始沸腾时,容器压力才会上升。
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 去求助
来源期刊
Nuclear Engineering and Design
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.
期刊最新文献
Analysis of risk-important LOCA sequences in NuScale considering accident tolerant fuels High-fidelity turbulence simulation for the OECD–NEA cold-leg mixing benchmark Development of a GPU-accelerated SN-DGM/JFNK full-core neutron transport solver with upwind sweeping and double-buffered strategy Neutronic and economic assessment of FeCrAl in CAREM 25 fuel cycle A Modelica subchannel code for liquid metal fast reactors: Development, validation, and auxiliary model sensitivity analysis
×
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:604180095
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