Development of three simulation tools for open-surface liquid metal magnetohydrodynamic flows in plasma-facing components using OpenFOAM

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
D. Suarez, S. Smolentsev
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引用次数: 0

Abstract

The use of open-surface liquid metal (LM) flows in plasma-facing components (PFC), namely the divertor and the first wall (FW) in large tokamak nuclear fusion reactors, promises several advantages compared to solid designs, such as reduced erosion and impurity retention. The current understanding of the flow dynamics governing open-surface liquid metals for PFC applications is incomplete. In this study, we develop and test three computational models to simulate open-surface magnetohydrodynamic (MHD) flows based on the OpenFOAM computational fluid dynamics (CFD) platform. The first model is 3D and is based on the volume of fluid (VoF) method for the interface capturing and on the electric potential formulation for the MHD effects. The second model is 2D. It also uses the VOF method but relies on the integration of the MHD effect in the plane perpendicular to the magnetic field; it allows for reducing one dimension in the direction of the magnetic field. The third model is 1D, it captures the interface using a height function, which simplifies the dimension perpendicular to the substrate, and also leverages the integration of the MHD effects in the plane perpendicular to the magnetic field. Our models couple several physical phenomena and involve special numerical techniques. The three models are validated against existing experimental results for LM flows in a horizontal non-conducting chute under a co-planar magnetic field. Further simulations of the same chute with electrically conducting walls are also presented in this work, showing the capability of the 3D model to couple different regions. While the 3D model identified well the complex flow behavior and the increase in the MHD drag, the simplified 1D and 2D models failed at providing accurate estimates of flow velocity and film height. The increased drag results in the formation of an MHD-induced hydraulic jump after certain distance from the inlet nozzle. The development of these models is a necessary step towards a better understanding of LM flows, which enables a successful design of technologies capable of protecting the PFC of a fusion reactor.
利用OpenFOAM开发三个面向等离子体组件的开放表面液态金属磁流体动力学流动仿真工具
在大型托卡马克核聚变反应堆的等离子体面组件(PFC)中,即分流器和第一壁(FW)中使用开放表面液态金属(LM)流,与固体设计相比有几个优点,例如减少侵蚀和杂质保留。目前对PFC应用的开表面液态金属流动动力学的理解是不完整的。在这项研究中,我们基于OpenFOAM计算流体动力学(CFD)平台开发并测试了三个计算模型来模拟开放表面磁流体动力学(MHD)流动。第一个模型是3D模型,基于流体体积(VoF)方法捕获界面,并基于MHD效应的电势公式。第二个模型是2D的。它也使用VOF方法,但依赖于MHD效应在垂直于磁场的平面上的积分;它允许在磁场方向上减小一个维度。第三种模型是1D,它使用高度函数捕获界面,这简化了垂直于基板的尺寸,并且还利用了垂直于磁场的平面上的MHD效应的集成。我们的模型结合了几种物理现象,并涉及特殊的数值技术。在共面磁场作用下,对水平非导电溜槽内LM流动的实验结果进行了验证。在这项工作中,还提出了具有导电壁的同一溜槽的进一步模拟,显示了3D模型耦合不同区域的能力。虽然3D模型可以很好地识别复杂的流动行为和MHD阻力的增加,但简化的1D和2D模型无法提供准确的流速和膜高度估计。增加的阻力导致在距离进口喷嘴一定距离后形成mhd诱导的水力跳变。这些模型的发展是更好地理解LM流程的必要步骤,这使得能够保护聚变反应堆PFC的技术设计成功。
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来源期刊
Fusion Engineering and Design
Fusion Engineering and Design 工程技术-核科学技术
CiteScore
3.50
自引率
23.50%
发文量
275
审稿时长
3.8 months
期刊介绍: The journal accepts papers about experiments (both plasma and technology), theory, models, methods, and designs in areas relating to technology, engineering, and applied science aspects of magnetic and inertial fusion energy. Specific areas of interest include: MFE and IFE design studies for experiments and reactors; fusion nuclear technologies and materials, including blankets and shields; analysis of reactor plasmas; plasma heating, fuelling, and vacuum systems; drivers, targets, and special technologies for IFE, controls and diagnostics; fuel cycle analysis and tritium reprocessing and handling; operations and remote maintenance of reactors; safety, decommissioning, and waste management; economic and environmental analysis of components and systems.
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