{"title":"Assessment of fluid-to-fluid similarity criteria to evaluate deterioration of heat transfer in flows of supercritical fluids","authors":"Chukwudi Azih","doi":"10.1016/j.nucengdes.2025.114683","DOIUrl":null,"url":null,"abstract":"<div><div>In nuclear reactors, heat exchangers, and power cycles operating at supercritical thermodynamic conditions, heat transfer deterioration is a concern for the design and safety of primary heat removal components. Such deterioration can cause localized excursions in surface temperature, potentially compromising the integrity of the pressure boundary that contains the pressurized coolant. Therefore, accurately predicting flow conditions that lead to this deterioration is essential. To address this, numerous studies have investigated heat transfer at supercritical fluid states using various working fluids, including water. Building on previously published similarity criteria, this work evaluates deteriorated heat transfer predictive criteria against a more comprehensive dataset of over 480 tests. Unlike conventional approaches that normalize based on pressure at the critical state, the updated similarity criteria define surrogate fluid states using state-space similarity with peak Prandtl number, which arguably has more relevance to the flow. Additionally, dynamic flow criteria were examined by comparing the Richardson number with other buoyancy parameters and relevant ranges of Reynolds numbers were specified. The assessments were conducted for tubular geometries under upward flow, downward flow, and horizontal flow conditions. Particularly strong results are observed for the upward flow dataset, which comprises more than half of the database tests. Based on these evaluations, new predictive correlations for deteriorated heat transfer are proposed, applicable across broad ranges of Reynolds numbers and buoyancy parameters and fluids.</div></div>","PeriodicalId":19170,"journal":{"name":"Nuclear Engineering and Design","volume":"448 ","pages":"Article 114683"},"PeriodicalIF":2.5000,"publicationDate":"2026-03-01","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/S002954932500860X","RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"2025/12/16 0:00:00","PubModel":"Epub","JCR":"Q1","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}
引用次数: 0
Abstract
In nuclear reactors, heat exchangers, and power cycles operating at supercritical thermodynamic conditions, heat transfer deterioration is a concern for the design and safety of primary heat removal components. Such deterioration can cause localized excursions in surface temperature, potentially compromising the integrity of the pressure boundary that contains the pressurized coolant. Therefore, accurately predicting flow conditions that lead to this deterioration is essential. To address this, numerous studies have investigated heat transfer at supercritical fluid states using various working fluids, including water. Building on previously published similarity criteria, this work evaluates deteriorated heat transfer predictive criteria against a more comprehensive dataset of over 480 tests. Unlike conventional approaches that normalize based on pressure at the critical state, the updated similarity criteria define surrogate fluid states using state-space similarity with peak Prandtl number, which arguably has more relevance to the flow. Additionally, dynamic flow criteria were examined by comparing the Richardson number with other buoyancy parameters and relevant ranges of Reynolds numbers were specified. The assessments were conducted for tubular geometries under upward flow, downward flow, and horizontal flow conditions. Particularly strong results are observed for the upward flow dataset, which comprises more than half of the database tests. Based on these evaluations, new predictive correlations for deteriorated heat transfer are proposed, applicable across broad ranges of Reynolds numbers and buoyancy parameters and fluids.
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.