Evaluating turbulence modeling for thermal–hydraulics analysis of molten salt reactors

IF 2.1 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Nuclear Engineering and Design Pub Date : 2025-02-01 Epub Date: 2024-12-24 DOI:10.1016/j.nucengdes.2024.113787
Ramiro Freile , Peter German, Mauricio Tano
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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 kϵ and kω 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.
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熔盐堆热工分析湍流模型的评价
本文研究了Reynolds average Navier Stokes (RANS)湍流模型对开芯熔盐堆(MSRs)热工分析的影响。文章的第一部分描述了最近在爱达荷国家实验室(INL)多物理场面向对象模拟环境(MOOSE)中引入的叉角羚的k−ε和k−ω SST RANS湍流模型。特别关注了两种模型中实现的近壁流建模策略及其在MOOSE中的计算实现。这两种模型都通过规范的实验数据进行了验证,这些数据类似于msr所期望的流动现象:通道流动、向后台阶和弯曲管道中的旋流。然后将这些模型应用于熔融氯化物反应堆实验(MCRE)的开源规范,为简洁起见,将其命名为莲花熔盐反应堆(L-MSR)。首先,将两种模型预测的流动现象和压降与预期反应堆运行条件的高保真LES模拟进行了比较。然后,评估了所选湍流模型对稳态温度场分布的影响。最后,对开放核msr湍流建模的选择方法提出了建议。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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来源期刊
Nuclear Engineering and Design
Nuclear Engineering and Design 工程技术-核科学技术
CiteScore
3.40
自引率
11.80%
发文量
377
审稿时长
5 months
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.
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