Fluid Flow Investigations within a 37 Element CANDU Fuel Bundle Supported by Magnetic Resonance Velocimetry and Computational Fluid Dynamics

Piro, M.H.A; Wassermann, F.; Grundmann, S.; Tensuda, B.; Kim, Seung Jun; Christon, M.; Berndt, Markus; Nishimura, M.; Tropea, C.

doi:10.1016/j.ijheatfluidflow.2017.04.010

Title: Fluid Flow Investigations within a 37 Element CANDU Fuel Bundle Supported by Magnetic Resonance Velocimetry and Computational Fluid Dynamics

Journal Article · Tue May 23 00:00:00 EDT 2017 · International Journal of Heat and Fluid Flow

DOI:https://doi.org/10.1016/j.ijheatfluidflow.2017.04.010· OSTI ID:1371668

Piro, M.H.A ^[1]; Wassermann, F. ^[2]; Grundmann, S. ^[3]; Tensuda, B. ^[4];

^[5]; Christon, M. ^[5];

^[5]; Nishimura, M. ^[6]; Tropea, C. ^[2]

Canadian Nuclear Labs., Chalk River, ON (Canada). Fuel and Fuel Channel Safety Branch
Technische Univ. Darmstadt (Germany). Dept. of Fluid Mechanics and Aerodynamics
Technische Univ. Darmstadt (Germany). Dept. of Fluid Mechanics and Aerodynamics; Univ. of Rostock (Germany). Inst. of Fluid Mechanics
Univ. of Toronto, ON (Canada). Inst. for Aerospace Sciences
Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
Canadian Nuclear Labs., Chalk River, ON (Canada). Fuel and Fuel Channel Safety Branch; Univ. of Waterloo, ON (Canada). Computer Science Dept.

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. Finally, 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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Research Organization:: Los Alamos National Laboratory (LANL), Los Alamos, NM (United States)

Sponsoring Organization:: USDOE National Nuclear Security Administration (NNSA)

Contributing Organization:: Collaborative with with Canadian Nuclear Laboratories (CNL)

Grant/Contract Number:: AC52-06NA25396; AC05-00OR22725

OSTI ID:: 1371668

Alternate ID(s):: OSTI ID: 1413776

Report Number(s):: LA-UR-15-27690

Journal Information:: International Journal of Heat and Fluid Flow, Vol. 66; ISSN 0142-727X

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

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Cited by: 18 works

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References (16)

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Title: Fluid Flow Investigations within a 37 Element CANDU Fuel Bundle Supported by Magnetic Resonance Velocimetry and Computational Fluid Dynamics

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