Life span assessment is a very important issue for the nuclear community. A serious threat to the life span of a Reactor Pressure Vessel (RPV) is an occurrence of the Pressurized Thermal Shock (PTS) during an Emergency Core Coolant (ECC) injection in a loss-of-coolant accident. Traditional system codes fail to predict the complex three-dimensional flow phenomena resulting from such an ECC injection. Improved results have been obtained using Computational Fluid Dynamics (CFD) analysis based on the Reynolds-Averaged Navier-Stokes (RANS) equations. However, it has been shown also that current transient RANS approaches are less capable to predict complex flow features in the downcomer of the RPV. More advanced CFD methods like Large-Eddy Simulation (LES) are required for modeling of these complex flow phenomena in the downcomer. The current paper addresses the feasibility of the application of LES for single-phase PTS. Furthermore, the required grid resolution for such LES analyses is identified by evaluation of solutions on different meshes. A buoyancy-driven PTS experiment has been considered. This experiment has been performed in the 1:5 linear scale Rossendorf Coolant Mixing Model (ROCOM) facility. In the applied numerical model, the incompressible Navier-Stokes equations are solved in the LES formulation, with an additional transport equation for a scalar, which is responsible for driving the embedded buoyancy term in the momentum equations. Instantaneous mixing characteristics are investigated based on evaluation of the scalar concentration. The analysis presented in this paper indicates that the application of LES is feasible nowadays. It is demonstrated that the mixing in the downcomer is quite sensitive to small turbulent disturbances at the ECC inlet, i.e., two simulations performed with slightly different fluctuations at inlet result in substantially different flow in the downcomer. This complicates the analysis of the data from simulations and suggests that validation against experimental data should not be performed using single physical experiment.
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17th International Conference on Nuclear Engineering
July 12–16, 2009
Brussels, Belgium
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-4355-0
PROCEEDINGS PAPER
Application of Large-Eddy Simulation to Pressurized Thermal Shock Problem
M. S. Loginov,
M. S. Loginov
Nuclear Research and Consultancy Group, Petten, The Netherlands
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E. M. J. Komen,
E. M. J. Komen
Nuclear Research and Consultancy Group, Petten, The Netherlands
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A. K. Kuczaj
A. K. Kuczaj
Nuclear Research and Consultancy Group, Petten, The Netherlands
Search for other works by this author on:
M. S. Loginov
Nuclear Research and Consultancy Group, Petten, The Netherlands
E. M. J. Komen
Nuclear Research and Consultancy Group, Petten, The Netherlands
A. K. Kuczaj
Nuclear Research and Consultancy Group, Petten, The Netherlands
Paper No:
ICONE17-75894, pp. 649-658; 10 pages
Published Online:
February 25, 2010
Citation
Loginov, MS, Komen, EMJ, & Kuczaj, AK. "Application of Large-Eddy Simulation to Pressurized Thermal Shock Problem." Proceedings of the 17th International Conference on Nuclear Engineering. Volume 5: Fuel Cycle and High and Low Level Waste Management and Decommissioning; Computational Fluid Dynamics (CFD), Neutronics Methods and Coupled Codes; Instrumentation and Control. Brussels, Belgium. July 12–16, 2009. pp. 649-658. ASME. https://doi.org/10.1115/ICONE17-75894
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