{"title":"Experimental investigation on interfacial area concentration in narrow-channel steam-water flow based on printed circuit sensor","authors":"Yiang Yang, Jinbiao Xiong","doi":"10.1016/j.nucengdes.2025.114091","DOIUrl":null,"url":null,"abstract":"<div><div>Due to deficiency of void fraction measurement of steam-water flow in narrow channels, existing interfacial area concentration (IAC) models for narrow channels have mostly been developed based on air–water flow. The applicability of these models to steam-water flow remains uncertain. To address this deficiency, a ceramic-substrate printed circuit (CSPC) sensor is utilized to obtain the instantaneous interface topology of steam-water flow in a narrow rectangular channel. Experiments were conducted under pressures ranging from 0.2 to 0.9 MPa, covering flow patterns from bubbly to annular flow. The average bubble shape, projected interfacial area concentration (PIAC), and projected interfacial length concentration (PILC) for bubbles of different sizes were comprehensively analyzed. The critical diameter separating distorted and cap bubbles, as utilized in existing IAC models, was verified from a statistical averaging perspective. Within the experimental conditions, PIAC and PILC showed no significant variation under different pressures. The case-averaged PIAC and PILC of steam-water flow and air–water flow exhibited good agreement within the same channel geometry, although some divergence was observed for bubbles of different sizes. Among the existing IAC correlations, the Yang-Xiong model demonstrated the best performance in predicting IAC compared to the present experimental data. The relative error of the total IAC was within ± 10 % for most cases and decreased with increasing void fraction.</div></div>","PeriodicalId":19170,"journal":{"name":"Nuclear Engineering and Design","volume":"439 ","pages":"Article 114091"},"PeriodicalIF":1.9000,"publicationDate":"2025-04-24","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/S0029549325002687","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
Due to deficiency of void fraction measurement of steam-water flow in narrow channels, existing interfacial area concentration (IAC) models for narrow channels have mostly been developed based on air–water flow. The applicability of these models to steam-water flow remains uncertain. To address this deficiency, a ceramic-substrate printed circuit (CSPC) sensor is utilized to obtain the instantaneous interface topology of steam-water flow in a narrow rectangular channel. Experiments were conducted under pressures ranging from 0.2 to 0.9 MPa, covering flow patterns from bubbly to annular flow. The average bubble shape, projected interfacial area concentration (PIAC), and projected interfacial length concentration (PILC) for bubbles of different sizes were comprehensively analyzed. The critical diameter separating distorted and cap bubbles, as utilized in existing IAC models, was verified from a statistical averaging perspective. Within the experimental conditions, PIAC and PILC showed no significant variation under different pressures. The case-averaged PIAC and PILC of steam-water flow and air–water flow exhibited good agreement within the same channel geometry, although some divergence was observed for bubbles of different sizes. Among the existing IAC correlations, the Yang-Xiong model demonstrated the best performance in predicting IAC compared to the present experimental data. The relative error of the total IAC was within ± 10 % for most cases and decreased with increasing void fraction.
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.