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

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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.