{"title":"Evaluating turbulence modeling for thermal–hydraulics analysis of molten salt reactors","authors":"Ramiro Freile , Peter German, Mauricio Tano","doi":"10.1016/j.nucengdes.2024.113787","DOIUrl":null,"url":null,"abstract":"<div><div>This article studies the impact of Reynolds Averaged Navier Stokes (RANS) turbulence modeling for the thermal–hydraulics analysis of open-core molten salt reactors (MSRs). The first part of the article describes the <span><math><mrow><mi>k</mi><mo>−</mo><mi>ϵ</mi></mrow></math></span> and <span><math><mrow><mi>k</mi><mo>−</mo><mi>ω</mi></mrow></math></span> SST RANS turbulence models recently introduced to Pronghorn in the Idaho National Laboratory’s (INL) Multiphysics Object-Oriented Simulation Environment (MOOSE). Special attention is given to the near-wall flow modeling strategies implemented in both models and their computational implementation in MOOSE. Both models are validated for canonical experimental data that resemble the flow phenomena expected for MSRs: a channel flow, a backward facing step, and swirling flow in a curved pipe. These models are then applied to the open-source specifications of the Molten Chloride Reactor Experiment (MCRE), which is named Lotus Molten Salt Reactor (L-MSR) for conciseness. First, the flow phenomena and pressure drops predicted by both models are compared with higher-fidelity LES simulations for the expected reactor operational conditions. Then, the impact of the selected turbulence model on steady-state temperature fields distribution is evaluated. Finally, recommendations are given for the selected approach to turbulence modeling of open-core MSRs.</div></div>","PeriodicalId":19170,"journal":{"name":"Nuclear Engineering and Design","volume":"432 ","pages":"Article 113787"},"PeriodicalIF":1.9000,"publicationDate":"2025-02-01","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/S0029549324008872","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
This article studies the impact of Reynolds Averaged Navier Stokes (RANS) turbulence modeling for the thermal–hydraulics analysis of open-core molten salt reactors (MSRs). The first part of the article describes the and SST RANS turbulence models recently introduced to Pronghorn in the Idaho National Laboratory’s (INL) Multiphysics Object-Oriented Simulation Environment (MOOSE). Special attention is given to the near-wall flow modeling strategies implemented in both models and their computational implementation in MOOSE. Both models are validated for canonical experimental data that resemble the flow phenomena expected for MSRs: a channel flow, a backward facing step, and swirling flow in a curved pipe. These models are then applied to the open-source specifications of the Molten Chloride Reactor Experiment (MCRE), which is named Lotus Molten Salt Reactor (L-MSR) for conciseness. First, the flow phenomena and pressure drops predicted by both models are compared with higher-fidelity LES simulations for the expected reactor operational conditions. Then, the impact of the selected turbulence model on steady-state temperature fields distribution is evaluated. Finally, recommendations are given for the selected approach to turbulence modeling of open-core MSRs.
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.