论文标题
高级反应器下降器中高prandtl数量流动流的直接数值模拟
Direct Numerical Simulation of High Prandtl Number Fluid Flow in the Downcomer of an Advanced Reactor
论文作者
论文摘要
被动安全是晚期核反应堆(Gen IV)设计的关键特征。在失去功率情景期间,下向来的角色起着至关重要的作用。下垂中的流体流动行为可能涉及被迫混合到自然对流并表征这些变化的方案的传热是一个艰巨的挑战。高分辨率传热数值数据库可以潜在地支持精确和负担得起的分辨率传热模型的发展。这些模型可以基于最近DOE资助的核能热流体应用卓越中心开发的多尺度层次结构设计。在本文中,下降器被简化为加热的平行板,并考虑了所有模拟的高prandtl数字流体(FLIBE)。在2个不同的Flibe PrandTL数字(12和24)的众多Richardson数字中进行了计算,这总共有40例模拟案例。研究时间平均和时间序列统计数据以及Nusselt数量相关性,以阐明混合对流行为。计算出的数据库将有助于理解降简流行为。最终,我们旨在评估现有的传热相关性,并针对没有令人满意的选择的情况进行一些修改。
The passive safety is a crucial feature of advanced nuclear reactor (Gen IV) design. During loss of power scenarios, the downcomer plays a crucial role. The fluid-flow behavior in the downcomer can involve forced to mixed to natural convection and characterizing the heat transfer for these changing regimes is a daunting challenge. High-resolution heat transfer numerical database can potentially support the development of precise and affordable reduced resolution heat transfer models. These models can be designed based on a multiscale hierarchy developed as part of the recently DOE-funded center of excellence for thermal-fluids applications in nuclear energy. In this paper, the downcomer is simplified to heated parallel plates and High Prandtl number fluid (FLiBe) is considered for all simulations. The calculations are performed for a wide range of Richardson number from 0 to 400 at 2 different FLiBe Prandtl numbers (12 and 24) which result in 40 simulated Cases in total. Time averaged and time series statistics as well as Nusselt number correlations are investigated to illuminate the mixed convection behaviors. The calculated database will be instrumental in understanding the flow behaviors in the downcomer. Ultimately, we aimed to evaluate existing heat transfer correlations and some modifications will be proposed for Cases where no satisfactory choice is available.