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Science and Technology of Nuclear Installations
Volume 2016 (2016), Article ID 3194839, 10 pages
Research Article

The Feasibility of Multidimensional CFD Applied to Calandria System in the Moderator of CANDU-6 PHWR Using Commercial and Open-Source Codes

1Severe Accident and PHWR Safety Research Division, Korea Atomic Energy Research Institute, Daejeon, Republic of Korea
2Department of Mechanical Engineering, Kunsan National University, Jeollabuk-do, Republic of Korea
3Department of Radiological Science, Konyang University, Daejeon, Republic of Korea

Received 17 May 2016; Revised 26 July 2016; Accepted 28 July 2016

Academic Editor: Michel Giot

Copyright © 2016 Hyoung Tae Kim et al. This is an open access article distributed under the Creative Commons Attribution License, which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.


The moderator system of CANDU, a prototype of PHWR (pressurized heavy-water reactor), has been modeled in multidimension for the computation based on CFD (computational fluid dynamics) technique. Three CFD codes are tested in modeled hydrothermal systems of heavy-water reactors. Commercial codes, COMSOL Multiphysics and ANSYS-CFX with OpenFOAM, an open-source code, are introduced for the various simplified and practical problems. All the implemented computational codes are tested for a benchmark problem of STERN laboratory experiment with a precise modeling of tubes, compared with each other as well as the measured data and a porous model based on the experimental correlation of pressure drop. Also the effect of turbulence model is discussed for these low Reynolds number flows. As a result, they are shown to be successful for the analysis of three-dimensional numerical models related to the calandria system of CANDU reactors.