半球形几何体内部加热自然对流的 CFD RANS 验证

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Daniele Dovizio , Boshen Bian , Walter Villanueva , Ed Komen
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引用次数: 0

摘要

在严重事故的背景下,一种已被证明适用于中低功率反应堆的缓解策略是熔融冕状体的舱内熔体滞留(IVMR)。因此,为使这一策略在高功率反应堆中可行,人们做出了许多努力。其中,欧洲 H2020 IVMR 项目的目标是评估和改进当前的建模策略,例如使用计算流体动力学 (CFD) 代码预测均质铈池中的流动和传热。由于存在明显的局限性,验证主要是根据现有的水基实验数据而不是铈混合物进行的。为了克服这一局限性,最近以直接数值模拟(DNS)的形式进行了补充性高保真数值模拟,并在当前工作中用作雷诺平均纳维-斯托克斯(RANS)方法验证的参考。更具体地说,RANS 数值模拟是使用 STAR-CCM+ 软件对三维半球形配置进行的。与 DNS 方法一致,布森斯克假设用于描述内部加热(IH)自然对流问题。流动条件对应的瑞利数和普朗特数分别为 0.5 和 0.5。在速度、温度、湍流动能的浮力产生和热通量方面,将 STAR-CCM+ 中通常用于浮力驱动流的几个湍流模型与 DNS 结果进行了比较和评估。RANS 模型获得了合理的结果,尤其是在预测流动构造的主要定性特征方面,如热分层、弯曲壁上的快速下降流和域顶的高湍流。RANS 和 DNS 之间的主要分歧出现在散体区域,所有 RANS 计算都呈现出强烈的再循环,而 DNS 计算则预测出一个扩展的近乎停滞的区域。此外,还进行了定量分析,强调了 RANS 方法的局限性,尤其是在湍流热通量建模方面,以及作为未来潜在工作开发更先进模型的必要性。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Validation of CFD RANS of an internally heated natural convection in a hemispherical geometry

In the context of severe accidents, one mitigation strategy that has been shown to work for low-to-intermediate power reactors is the In-Vessel Melt Retention (IVMR) of molten corium. For this reason, several efforts have been put forward to make this strategy feasible for high power reactors. In particular, the aim of the European H2020 IVMR project was to evaluate and improve current modeling strategies, such as the use of Computational Fluid Dynamics (CFD) codes for the prediction of flow and heat transfer in a homogeneous corium pool. Due to evident limitations, the validation was mainly performed against an available water-based experimental data, rather than a corium mixture. In order to overcome this limitation, complementary high fidelity numerical simulations, in the form of Direct Numerical Simulation (DNS), have been performed recently and are used in the current work as a reference for the validation purposes of the Reynolds Averaged Navier–Stokes (RANS) approach. More specifically, RANS numerical simulations of a three-dimensional hemispherical configuration are performed using the STAR-CCM+ software. Consistent with the DNS approach, the Boussinesq assumption is used to characterize the internally heated (IH) natural convection problem. The flow conditions correspond to a Rayleigh number of 1.61011 and a Prandtl number of 0.5. Several turbulence models available in STAR-CCM+, which are generally used for buoyancy driven flows, are compared and evaluated against the DNS results, in terms of velocity, temperature, buoyancy production of the turbulent kinetic energy and heat flux. Reasonable results are obtained by the RANS models, especially in predicting the main qualitative features of the flow configuration, such as thermal stratification, fast descending flow on the curved walls and high turbulence at the top of the domain. The main divergence between RANS and DNS is observed in the bulk region, where all the RANS computations present strong recirculation, while an extended nearly stagnant zone is predicted by DNS calculations. A quantitative analysis is performed as well, highlighting the limitations of the RANS approaches, especially for the turbulent heat flux modeling, and the need for the development of more advanced models as potential future efforts.

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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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