{"title":"波动振动下水平管道中气液两相流的空隙率研究","authors":"Yunlong Zhou, Yiwen Ran, Qichao Liu, Shibo Zhang","doi":"10.1016/j.nucengdes.2024.113710","DOIUrl":null,"url":null,"abstract":"<div><div>Accurate prediction of void fraction of gas–liquid two-phase flow under fluctuating vibration is crucial for the safe and stable operation of floating nuclear power plants. The void fraction characteristics of gas–liquid two-phase flow in horizontal pipe under different vibration conditions are studied experimentally. The results showed that the void fraction of bubbly flow and intermittent flow varies considerably under fluctuating vibration, whereas changes in stratified flow and annular flow are less pronounced. Generally speaking, the void fraction first increases and then decreases with the increase of pipe diameter, while the increase of vibration frequency and amplitude cause a nonlinear variation in the void fraction. Evaluation of void fraction calculation models for stationary pipes reveals that existing models have significant prediction errors for bubbly flow and intermittent flow void fractions. By considering the effects of pipe diameter and vibration parameters, the Froude number of liquid phase is introduced to develop a void fraction calculation model for bubbly flow and intermittent flow. The Mean Absolute Relative Difference (MARD) of new established model is 10.66% and 12.06%. This significantly improved the prediction accuracy of the void fraction under fluctuating vibration.</div></div>","PeriodicalId":19170,"journal":{"name":"Nuclear Engineering and Design","volume":"431 ","pages":"Article 113710"},"PeriodicalIF":1.9000,"publicationDate":"2024-11-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"Investigation on void fraction of gas–liquid two-phase flow in horizontal pipe under fluctuating vibration\",\"authors\":\"Yunlong Zhou, Yiwen Ran, Qichao Liu, Shibo Zhang\",\"doi\":\"10.1016/j.nucengdes.2024.113710\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><div>Accurate prediction of void fraction of gas–liquid two-phase flow under fluctuating vibration is crucial for the safe and stable operation of floating nuclear power plants. The void fraction characteristics of gas–liquid two-phase flow in horizontal pipe under different vibration conditions are studied experimentally. The results showed that the void fraction of bubbly flow and intermittent flow varies considerably under fluctuating vibration, whereas changes in stratified flow and annular flow are less pronounced. Generally speaking, the void fraction first increases and then decreases with the increase of pipe diameter, while the increase of vibration frequency and amplitude cause a nonlinear variation in the void fraction. Evaluation of void fraction calculation models for stationary pipes reveals that existing models have significant prediction errors for bubbly flow and intermittent flow void fractions. By considering the effects of pipe diameter and vibration parameters, the Froude number of liquid phase is introduced to develop a void fraction calculation model for bubbly flow and intermittent flow. The Mean Absolute Relative Difference (MARD) of new established model is 10.66% and 12.06%. This significantly improved the prediction accuracy of the void fraction under fluctuating vibration.</div></div>\",\"PeriodicalId\":19170,\"journal\":{\"name\":\"Nuclear Engineering and Design\",\"volume\":\"431 \",\"pages\":\"Article 113710\"},\"PeriodicalIF\":1.9000,\"publicationDate\":\"2024-11-26\",\"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/S0029549324008100\",\"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/S0029549324008100","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}
Investigation on void fraction of gas–liquid two-phase flow in horizontal pipe under fluctuating vibration
Accurate prediction of void fraction of gas–liquid two-phase flow under fluctuating vibration is crucial for the safe and stable operation of floating nuclear power plants. The void fraction characteristics of gas–liquid two-phase flow in horizontal pipe under different vibration conditions are studied experimentally. The results showed that the void fraction of bubbly flow and intermittent flow varies considerably under fluctuating vibration, whereas changes in stratified flow and annular flow are less pronounced. Generally speaking, the void fraction first increases and then decreases with the increase of pipe diameter, while the increase of vibration frequency and amplitude cause a nonlinear variation in the void fraction. Evaluation of void fraction calculation models for stationary pipes reveals that existing models have significant prediction errors for bubbly flow and intermittent flow void fractions. By considering the effects of pipe diameter and vibration parameters, the Froude number of liquid phase is introduced to develop a void fraction calculation model for bubbly flow and intermittent flow. The Mean Absolute Relative Difference (MARD) of new established model is 10.66% and 12.06%. This significantly improved the prediction accuracy of the void fraction under fluctuating vibration.
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.