{"title":"Three-Field subchannel modeling of CANDU fuel thermal-hydraulics with MEFISTO-T code","authors":"Jean-Marie Le Corre","doi":"10.1016/j.nucengdes.2025.114405","DOIUrl":null,"url":null,"abstract":"<div><div>To support the development and validation of core thermal–hydraulic simulation codes, OECD/NEA organized a benchmark focused on thermal–hydraulic behavior of CANDU fuel assemblies. The benchmark was based on full-scale heat transfer experiments conducted in a 28-element horizontal test bundle, covering conditions representative of CANDU core operations. A non-blind phase was included, providing a limited set of axial pressure drop (single-phase and two-phase) and critical power data, followed by a blind phase for predictive assessment. The tested geometries simulated CANDU pressure tubes under both uncrept and crept (i.e., aging) conditions, as well as two different bearing pad heights. The crept geometry introduces a significant bypass on the upper side of the rod bundle, associated with complex crossflows that are notoriously challenging to capture by simulation codes. The Westinghouse MEFISTO-T subchannel analysis code, employing a mechanistic three-field model of annular two-phase flow and originally developed for BWR fuel applications, was applied to simulate all benchmark cases. The code calibration parameters related to form loss and drop deposition enhancement due to structural components were adjusted based on the provided dataset. For the non-blind phase, the code accurately predicts axial pressure drop and critical power, and correctly identifies the dryout rod and orientation, although with a downstream bias in axial location. Further results from the blind phase demonstrate generally good agreement, particularly in capturing the effect of pressure tube creep on axial pressure drop and the influence of system parameters (pressure, mass flow rate and inlet temperature) on critical power. However, the significant reduction in critical power observed in the tests due to pressure tube creep and lower bearing pad height was underpredicted, indicating areas for further model refinement. These results highlight the strong potential of applying the MEFISTO-T three-field model to CANDU fuel geometry, while also revealing opportunities for further improvements.</div></div>","PeriodicalId":19170,"journal":{"name":"Nuclear Engineering and Design","volume":"445 ","pages":"Article 114405"},"PeriodicalIF":2.1000,"publicationDate":"2025-09-05","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/S0029549325005825","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
To support the development and validation of core thermal–hydraulic simulation codes, OECD/NEA organized a benchmark focused on thermal–hydraulic behavior of CANDU fuel assemblies. The benchmark was based on full-scale heat transfer experiments conducted in a 28-element horizontal test bundle, covering conditions representative of CANDU core operations. A non-blind phase was included, providing a limited set of axial pressure drop (single-phase and two-phase) and critical power data, followed by a blind phase for predictive assessment. The tested geometries simulated CANDU pressure tubes under both uncrept and crept (i.e., aging) conditions, as well as two different bearing pad heights. The crept geometry introduces a significant bypass on the upper side of the rod bundle, associated with complex crossflows that are notoriously challenging to capture by simulation codes. The Westinghouse MEFISTO-T subchannel analysis code, employing a mechanistic three-field model of annular two-phase flow and originally developed for BWR fuel applications, was applied to simulate all benchmark cases. The code calibration parameters related to form loss and drop deposition enhancement due to structural components were adjusted based on the provided dataset. For the non-blind phase, the code accurately predicts axial pressure drop and critical power, and correctly identifies the dryout rod and orientation, although with a downstream bias in axial location. Further results from the blind phase demonstrate generally good agreement, particularly in capturing the effect of pressure tube creep on axial pressure drop and the influence of system parameters (pressure, mass flow rate and inlet temperature) on critical power. However, the significant reduction in critical power observed in the tests due to pressure tube creep and lower bearing pad height was underpredicted, indicating areas for further model refinement. These results highlight the strong potential of applying the MEFISTO-T three-field model to CANDU fuel geometry, while also revealing opportunities for further improvements.
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.