{"title":"Validation of a system code (GAMMA+) using standard k-ε model for multi-dimensional turbulent flows in various geometries","authors":"Seung Hyun Yoon, Nam-il Tak, Hong Sik Lim","doi":"10.1016/j.nucengdes.2025.114079","DOIUrl":null,"url":null,"abstract":"<div><div>The GAMMA+ (General Analyzer for Multi-component and Multi-dimensional Transient Application) has been developed as a safety analysis tool for non-light water reactors (non-LWRs). Multi-dimensional turbulence modeling capabilities in system codes are essential for analyzing rapid transients in non-LWR nuclear systems with large cores operating in turbulent regimes. While some system codes employ the mixing-length model due to its implementation simplicity, the standard k-ε model is preferred for its superior accuracy and robustness in practical flow applications. This study presents the implementation of the standard k-ε model into GAMMA+, utilizing a square matrix that consists of the temporal differences of the pressure, the temperature, k and ε. Validation of the implemented model encompassed various single-phase flow configurations: flows in a pipe, a plate channel, and a backward-facing step with adiabatic wall conditions; forced convection flows including a pipe, an abruptly expanded pipe, and a backward-facing step with heat flux conditions; and natural convection flows in cavities with fixed temperature boundaries. Comparative analyses against experimental data, Direct Numerical Simulation (DNS) results, and Reynolds-Averaged Navier Stokes (RANS) simulations from well-known computational fluid dynamics (CFD) codes demonstrate the successful implementation of the standard k-ε model in GAMMA+ for multi-dimensional turbulent flow simulations.</div></div>","PeriodicalId":19170,"journal":{"name":"Nuclear Engineering and Design","volume":"439 ","pages":"Article 114079"},"PeriodicalIF":1.9000,"publicationDate":"2025-04-25","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/S0029549325002560","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
The GAMMA+ (General Analyzer for Multi-component and Multi-dimensional Transient Application) has been developed as a safety analysis tool for non-light water reactors (non-LWRs). Multi-dimensional turbulence modeling capabilities in system codes are essential for analyzing rapid transients in non-LWR nuclear systems with large cores operating in turbulent regimes. While some system codes employ the mixing-length model due to its implementation simplicity, the standard k-ε model is preferred for its superior accuracy and robustness in practical flow applications. This study presents the implementation of the standard k-ε model into GAMMA+, utilizing a square matrix that consists of the temporal differences of the pressure, the temperature, k and ε. Validation of the implemented model encompassed various single-phase flow configurations: flows in a pipe, a plate channel, and a backward-facing step with adiabatic wall conditions; forced convection flows including a pipe, an abruptly expanded pipe, and a backward-facing step with heat flux conditions; and natural convection flows in cavities with fixed temperature boundaries. Comparative analyses against experimental data, Direct Numerical Simulation (DNS) results, and Reynolds-Averaged Navier Stokes (RANS) simulations from well-known computational fluid dynamics (CFD) codes demonstrate the successful implementation of the standard k-ε model in GAMMA+ for multi-dimensional turbulent flow simulations.
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.