The paper focuses on the extension of the NEK-2P Wall Heat Transfer model, which was initially developed for the analysis of Critical Heat Flux (CHF) under Dryout (DO) conditions to the simulation of CHF under Departure from Nucleate Boiling (DNB) conditions. The paper presents results of recent NEK-2P analyses of several CHF experiments including both DO and DNB conditions. The CHF experiments analyzed have measured the axial distribution of wall temperatures in two-phase boiling flow in a vertical channel with a heated wall. The axial distribution of the calculated wall temperatures is compared with the corresponding experimental data. Reasonably good agreement with measured data is obtained in predicting the CHF location and post CHF wall temperature magnitudes illustrating the ability of the NEK-2P code and Extended Boiling Framework (EBF) models to simulate the CHF phenomena for a wide range of thermal-hydraulic conditions.
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2018 26th International Conference on Nuclear Engineering
July 22–26, 2018
London, England
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5152-4
PROCEEDINGS PAPER
Advances in Modeling Critical Heat Flux in LWR Boiling Flows With the NEK-2P CFD Code
Adrian Tentner,
Adrian Tentner
Argonne National Laboratory, Argonne, IL
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Prasad Vegendla,
Prasad Vegendla
Argonne National Laboratory, Argonne, IL
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Ananias Tomboulides,
Ananias Tomboulides
Argonne National Laboratory, Argonne, IL
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Aleks Obabko,
Aleks Obabko
Argonne National Laboratory, Argonne, IL
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Elia Merzari,
Elia Merzari
Argonne National Laboratory, Argonne, IL
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Dillon Shaver
Dillon Shaver
Argonne National Laboratory, Argonne, IL
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Adrian Tentner
Argonne National Laboratory, Argonne, IL
Prasad Vegendla
Argonne National Laboratory, Argonne, IL
Ananias Tomboulides
Argonne National Laboratory, Argonne, IL
Aleks Obabko
Argonne National Laboratory, Argonne, IL
Elia Merzari
Argonne National Laboratory, Argonne, IL
Dillon Shaver
Argonne National Laboratory, Argonne, IL
Paper No:
ICONE26-81910, V008T09A030; 11 pages
Published Online:
October 24, 2018
Citation
Tentner, A, Vegendla, P, Tomboulides, A, Obabko, A, Merzari, E, & Shaver, D. "Advances in Modeling Critical Heat Flux in LWR Boiling Flows With the NEK-2P CFD Code." Proceedings of the 2018 26th International Conference on Nuclear Engineering. Volume 8: Computational Fluid Dynamics (CFD); Nuclear Education and Public Acceptance. London, England. July 22–26, 2018. V008T09A030. ASME. https://doi.org/10.1115/ICONE26-81910
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