A Validation Experiment for Turbulent Mixing in a Collated Jet

I. Craig, Coleman D. Hoff, Paul J. Kristo, M. Kimber
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引用次数: 1

Abstract

Numerical modeling of turbulent mixing is complicated not only by the natural complexity of the flow physics, but by the model sensitivity to the user specified conditions. When aiming to quantify the level of trust in a given model, a validation experiment is often performed to provide data against which confidence comparisons can be made, ultimately evaluating the adequacy of the model assumptions. In the nuclear community, a number of promising Generation IV reactor concepts have been proposed, each requiring high fidelity modeling capabilities to accurately assess safety related issues. The experiment described in this paper is intended to provide a much needed validation data set to assess the use of computational fluid dynamics (CFD) in a complex turbulent mixing scenario relevant to the prismatic very high temperature reactor (VHTR) concept. Over the course of the VHTR’s operation, the reactor’s graphite moderated hexagonal fuel blocks shrink from neutron damage, forming interstitial gaps between adjacent blocks. A significant percentage of the coolant can flow through these gaps, having a substantial impact on the thermal-hydraulic conditions in the core. An experimental facility is presented that uses air as a simulant fluid and includes a unit cell representation of the hexagonal blocks, which accounts for both the intended circular channels and secondary rectangular slot features induced by the bypass gaps. The outlet of the unit cell consists of a collated jet consisting of a central round jet surrounded by three slot jets at relative 120° angles to one another issuing into a stagnant domain. A preliminary test case is proposed in which the collated jet is set to an isothermal and iso-velocity condition. Constant temperature anemometry (CTA) and constant current anemometry (CCA) measurements serve to capture the velocity and temperature inlet quantities (IQs). Particle image velocimetry (PIV) measurements provide the appropriate system response quantities (SRQs), yielding insight into the mean and fluctuating components of the 2-D velocity field. Results are presented in the range of 0–8 diameters downstream of the inlet to the test section. The collated jet inlet region yields velocity profiles that are heavily influenced by opposing pressure gradients between the neighboring round and slot regions. As a result, the velocity peaks found in this area are neither in the centerline of the round jet nor that of the slot, but are towards the outer edge of each. With increasing downstream distance, the collated jet is found to exhibit a more classical round jet profile. The inlet region of the collated jet is thus of particular interest to future modeling efforts to more accurately depict the lower plenum behavior and transition to a self-similar profile downstream. Proper uncertainty quantification is also presented, and aids in assessing the integrity of the experimental results for future CFD validation.
整理射流湍流混合的验证实验
湍流混合数值模拟的复杂性不仅在于流动物理的自然复杂性,还在于模型对用户指定条件的敏感性。当目标是量化给定模型中的信任水平时,通常执行验证实验以提供可以进行置信度比较的数据,最终评估模型假设的充分性。在核领域,已经提出了许多有前途的第四代反应堆概念,每个概念都需要高保真度建模能力,以准确评估安全相关问题。本文中描述的实验旨在提供一个急需的验证数据集,以评估计算流体动力学(CFD)在与棱镜极高温反应器(VHTR)概念相关的复杂湍流混合场景中的使用。在VHTR的运行过程中,反应堆的石墨慢化六边形燃料块因中子损伤而收缩,在相邻块之间形成间隙。相当大比例的冷却剂可以流过这些间隙,对堆芯的热工条件产生重大影响。提出了一种实验装置,它使用空气作为模拟流体,并包括六边形块的单元格表示,它既考虑了预期的圆形通道,也考虑了由旁路间隙引起的二次矩形槽特征。单元格的出口由一个排列整齐的射流组成,该射流由一个中心圆形射流组成,周围环绕着三个槽状射流,彼此成120°的相对角度,向一个停滞区域发出。提出了一种初步的测试用例,将整理后的射流设置为等温等速条件。恒温风速测量(CTA)和恒流风速测量(CCA)用于捕获速度和温度入口量(iq)。粒子图像测速(PIV)测量提供适当的系统响应量(SRQs),从而深入了解二维速度场的平均和波动分量。结果是在入口到测试段下游0-8直径范围内给出的。经过整理的射流入口区域产生的速度分布很大程度上受到相邻圆区和槽区之间相反压力梯度的影响。因此,在这个区域发现的速度峰值既不在圆射流的中心线上,也不在槽的中心线上,而是朝向各自的外缘。随着下游距离的增加,整理后的射流呈现出更经典的圆形射流轮廓。因此,经过整理的射流的入口区域对未来的建模工作特别感兴趣,以更准确地描述下层静压室的行为并向下游的自相似剖面过渡。适当的不确定度量化也提出,并有助于评估实验结果的完整性,为未来的CFD验证。
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