{"title":"超临界自然循环回路数值热水力分析","authors":"A.K. Vias , V.K. Garg , P.K. Vijayan , G. Dutta","doi":"10.1016/j.nucengdes.2025.114457","DOIUrl":null,"url":null,"abstract":"<div><div>In the present numerical study, a supercritical natural circulation loop (SCNCL) with a closed configuration is analyzed from a thermal-hydraulic (TH) perspective. An in-house model is developed to capture the axial variation of TH field variables considering a single channel in the heated section. This TH model efficiently accounts for local property variations at supercritical pressures and is integrated with models for the pressurizer, cooling heat exchanger (CHX), and wall heat conduction to accurately represent the behavior of a closed SCNCL. To evaluate the predictive capability of the integrated TH model, validation is performed against both experimental data and numerical results available in the literature, covering steady state and transient scenarios. Steady state simulations are then conducted to assess the SCNCL performance and determine the mass flow rate under various operating conditions, with an emphasis on identifying the underlying physical mechanisms. Finally, transient simulations are carried out to investigate the risk of density wave oscillations (DWOs) and to determine the marginal stability boundary (MSB). A comprehensive parametric study is performed to explore the influence of different factors on the MSB.</div></div>","PeriodicalId":19170,"journal":{"name":"Nuclear Engineering and Design","volume":"445 ","pages":"Article 114457"},"PeriodicalIF":2.1000,"publicationDate":"2025-09-20","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"Numerical thermal hydraulic analysis of supercritical natural circulation loop\",\"authors\":\"A.K. Vias , V.K. Garg , P.K. Vijayan , G. Dutta\",\"doi\":\"10.1016/j.nucengdes.2025.114457\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><div>In the present numerical study, a supercritical natural circulation loop (SCNCL) with a closed configuration is analyzed from a thermal-hydraulic (TH) perspective. An in-house model is developed to capture the axial variation of TH field variables considering a single channel in the heated section. This TH model efficiently accounts for local property variations at supercritical pressures and is integrated with models for the pressurizer, cooling heat exchanger (CHX), and wall heat conduction to accurately represent the behavior of a closed SCNCL. To evaluate the predictive capability of the integrated TH model, validation is performed against both experimental data and numerical results available in the literature, covering steady state and transient scenarios. Steady state simulations are then conducted to assess the SCNCL performance and determine the mass flow rate under various operating conditions, with an emphasis on identifying the underlying physical mechanisms. Finally, transient simulations are carried out to investigate the risk of density wave oscillations (DWOs) and to determine the marginal stability boundary (MSB). A comprehensive parametric study is performed to explore the influence of different factors on the MSB.</div></div>\",\"PeriodicalId\":19170,\"journal\":{\"name\":\"Nuclear Engineering and Design\",\"volume\":\"445 \",\"pages\":\"Article 114457\"},\"PeriodicalIF\":2.1000,\"publicationDate\":\"2025-09-20\",\"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/S002954932500634X\",\"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/S002954932500634X","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}
Numerical thermal hydraulic analysis of supercritical natural circulation loop
In the present numerical study, a supercritical natural circulation loop (SCNCL) with a closed configuration is analyzed from a thermal-hydraulic (TH) perspective. An in-house model is developed to capture the axial variation of TH field variables considering a single channel in the heated section. This TH model efficiently accounts for local property variations at supercritical pressures and is integrated with models for the pressurizer, cooling heat exchanger (CHX), and wall heat conduction to accurately represent the behavior of a closed SCNCL. To evaluate the predictive capability of the integrated TH model, validation is performed against both experimental data and numerical results available in the literature, covering steady state and transient scenarios. Steady state simulations are then conducted to assess the SCNCL performance and determine the mass flow rate under various operating conditions, with an emphasis on identifying the underlying physical mechanisms. Finally, transient simulations are carried out to investigate the risk of density wave oscillations (DWOs) and to determine the marginal stability boundary (MSB). A comprehensive parametric study is performed to explore the influence of different factors on the MSB.
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.