Computational modeling of the fluid/thermal fields inside the moderator of CANDU reactors

该建议旨在确定布鲁斯A和皮克林A两个不同核反应堆内慢化剂流动的流体和热行为，以及按比例缩小试验设施的建模。后者的设计目的是进行小规模试验。由于系统的复杂性，很难使用广义的缩放参数，如雷诺数和阿基米德数来缩小实际反应堆的比例。本研究的目的是为缩小测试设施的规模和设计制定标准。为了实现这一目标，首先使用计算流体动力学（CFD）建模，确定真实反应堆的流体/热行为信息。然后，将获得一个按比例缩小的测试系统的入口流动特性以及功率输入，以便它提供与实际反应堆相似的流体/热。我们以前使用CFD建模来模拟几种不同的调节剂。结果揭示了慢化剂内部流体流动和温度模式的细节。在目前的研究中，提出了布鲁斯A和皮克林A内部慢化剂流动的大涡流模拟（LES）。

This proposal is aimed at determining the fluid and thermal behavior of the moderator flows inside two different nuclear reactors, namely, Bruce A and Pickering A, as well as modeling of a scaled down test facility. The latter is being designed to perform small scale tests. Because of the complexityof the system, it is difficult to use generalized scaling parameters, such as Reynolds and Archimedes numbers to scale down a real reactor. The present studyis aimed at developing criteria for the scaling and design of a scaled down testing facility. In order to achieve this goal, first using Computational Fluid Dynamics (CFD) modeling, the information on the fluid/thermal behavior of a real reactor will be determined. Then the inlet flow characteristics as well as the power inputs for a scaled down testing system will be obtained so that it provides similar fluid/thermal as in thereal reactor. We have previouslyused CFD modeling to simulate several different moderators. The results haverevealed details of the fluid flow and temperature patterns inside the moderator. In the current study, large eddysimulation (LES) of the moderator flows inside of Bruce A and Pickering A are proposed.