Abstract MYRRHA is a pool-type research reactor under design at the Belgian nuclear research center SCK·CEN. The multi-purpose fast-spectrum MYRRHA reactor is cooled with lead–bismuth eutectic (LBE). ESCAPE is a thermal hydraulic 1/6th-scale model of the MYRRHA reactor developed within the European framework programs THINS and MYRTE. The experiments from ESCAPE are crucial for the design and licensing of MYRRHA. First of all, these experiments can provide information on the flow patterns and heat transport in the different compartments of the reactor. Secondly, the data from the ESCAPE experiments can be used for qualification of thermal hydraulic computer codes that will be applied for analyzing the flow and heat transport in the MYRRHA reactor. Considering the rare and typical conditions in heavy liquid cooled nuclear reactors, thorough validation of these codes against relevant experimental data is a prerequisite before application. This paper presents the approach followed by NRG to model the flow and heat transport in ESCAPE using the Computational Fluid Dynamics (CFD) code STAR-CCM+. CFD analyses for different forced flow conditions are presented and compared with experimental results. The predicted temperature distribution in the pool, core and plena agrees well with the temperature measurements from ESCAPE.

中文翻译：

---

针对池实验验证 CFD 分析 ESCAPE

摘要 MYRRHA 是比利时核研究中心SCK·CEN 正在设计的池式研究堆。多用途快谱 MYRRHA 反应堆由铅铋共晶 (LBE) 冷却。ESCAPE 是在欧洲框架计划 THINS 和 MYRTE 内开发的 MYRRHA 反应堆的热力液压 1/6 比例模型。ESCAPE 的实验对于 MYRRHA 的设计和许可至关重要。首先，这些实验可以提供有关反应堆不同隔室中流动模式和热传递的信息。其次，来自 ESCAPE 实验的数据可用于验证热力液压计算机代码，这些代码将用于分析 MYRRHA 反应器中的流动和热传输。考虑到重液冷核反应堆中罕见的典型条件，根据相关实验数据对这些代码进行彻底验证是应用前的先决条件。本文介绍了 NRG 使用计算流体动力学 (CFD) 代码 STAR-CCM+ 对 ESCAPE 中的流动和热传递进行建模的方法。介绍了不同强制流动条件的 CFD 分析，并与实验结果进行了比较。水池、核心和斑块中的预测温度分布与 ESCAPE 的温度测量结果非常吻合。