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引用次数: 0
摘要
GAMMA+(多组分和多维瞬态应用通用分析仪)是一种用于非轻水反应堆(non-LWRs)的安全分析工具。系统代码中的多维湍流建模能力对于分析在湍流状态下运行的大堆芯非轻堆核系统的快速瞬态是必不可少的。虽然一些系统代码由于实现简单而采用混合长度模型,但标准k-ε模型在实际流动应用中具有较高的精度和鲁棒性,因此更受青睐。本研究提出了标准k-ε模型在GAMMA+中的实现,利用由压力、温度、k和ε的时间差异组成的方阵。所实现模型的验证包括各种单相流配置:管道、板形通道和具有绝热壁条件的后向台阶中的流动;强制对流流包括管道、突然膨胀的管道和具有热流条件的后面向台阶;自然对流在有固定温度边界的空腔中流动。与实验数据、直接数值模拟(DNS)结果和著名计算流体动力学(CFD)代码的reynolds - average Navier Stokes (RANS)模拟进行对比分析表明,GAMMA+中标准k-ε模型成功实现了多维湍流模拟。
Validation of a system code (GAMMA+) using standard k-ε model for multi-dimensional turbulent flows in various geometries
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.