Fluid flow investigations within a 37 element CANDU fuel bundle supported by magnetic resonance velocimetry and computational fluid dynamics |
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| Institution: | 1. Fuel and Fuel Channel Safety Branch, Canadian Nuclear Laboratories, Chalk River, ON, Canada;2. Department of Fluid Mechanics and Aerodynamics, Technische Universität Darmstadt, Darmstadt, Germany;3. Institute of Fluid Mechanics, University of Rostock, Rostock, Germany;4. University of Toronto Institute for Aerospace Sciences, University of Toronto, Toronto, ON, Canada;5. Nuclear Engineering and Nonproliferation, Los Alamos National Laboratory, Los Alamos, NM 87545, USA;6. Computational Sciences International, Los Alamos, NM 87544, USA;7. Computer, Computational and Statistical Sciences, Los Alamos National Laboratory, Los Alamos, NM 87545, USA;8. Computer Science Department, University of Waterloo, Waterloo, ON, Canada;1. Department of Mechanical and Aerospace Engineering, North Carolina State University, Raleigh, NC 27695, USA;2. School of Mathematics and Systems Science, Beihang University, Beijing 100191, PR China;3. Computational Physics and Methods Group, Los Alamos National Laboratory, Los Alamos, NM 87545-0001, USA |
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| Abstract: | The current work presents experimental and computational investigations of fluid flow through a 37 element CANDU nuclear fuel bundle. Experiments based on Magnetic Resonance Velocimetry (MRV) permit three-dimensional, three-component fluid velocity measurements to be made within the bundle with sub-millimeter resolution that are non-intrusive, do not require tracer particles or optical access of the flow field. Computational fluid dynamic (CFD) simulations of the foregoing experiments were performed with the hydra-th code using implicit large eddy simulation, which were in good agreement with experimental measurements of the fluid velocity. Greater understanding has been gained in the evolution of geometry-induced inter-subchannel mixing, the local effects of obstructed debris on the local flow field, and various turbulent effects, such as recirculation, swirl and separation. These capabilities are not available with conventional experimental techniques or thermal-hydraulic codes. The overall goal of this work is to continue developing experimental and computational capabilities for further investigations that reliably support nuclear reactor performance and safety. |
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