Modeling of two-phase boiling flow and critical heat flux with the NEK-2P CFD code

Adrian Tentner, Prasad Vegendla, Ananias Tomboulides, Aleks Obabko, Elia Merzari, Dillon Shaver

Research output: Chapter in Book/Report/Conference proceedingConference contribution

6 Citations (Scopus)

Abstract

The paper focuses on the development, implementation, and initial validation of the NEK-2P two-fluid two-phase model. Recent extensions of the Extended Boiling Framework (EBF) models are presented, including the implementation of a four-field two-phase topology which replaces the previous twofield two-phase approach. The paper presents results of recent NEK-2P analyses of several CHF experiments. Good agreement between the simulated wall temperatures and measured data is observed. The simulation results predict well both the dryout location and post dryout wall temperature magnitudes, illustrating the ability of the NEK-2P code and extended EBF models to simulate the CHF phenomena for a range of thermal-hydraulic conditions.

Original languageEnglish (US)
Title of host publicationComputational Fluid Dynamics (CFD) and Coupled Codes; Nuclear Education, Public Acceptance and Related Issues
PublisherAmerican Society of Mechanical Engineers (ASME)
ISBN (Print)9784888982566
DOIs
StatePublished - Jan 1 2017
Event2017 25th International Conference on Nuclear Engineering, ICONE 2017 - Shanghai, China
Duration: Jul 2 2017Jul 6 2017

Publication series

NameInternational Conference on Nuclear Engineering, Proceedings, ICONE
Volume8

Conference

Conference2017 25th International Conference on Nuclear Engineering, ICONE 2017
CountryChina
CityShanghai
Period7/2/177/6/17

Fingerprint

Boiling liquids
Heat flux
Computational fluid dynamics
Hydraulics
Topology
Temperature
Fluids
Experiments
Hot Temperature

All Science Journal Classification (ASJC) codes

  • Nuclear Energy and Engineering

Cite this

Tentner, A., Vegendla, P., Tomboulides, A., Obabko, A., Merzari, E., & Shaver, D. (2017). Modeling of two-phase boiling flow and critical heat flux with the NEK-2P CFD code. In Computational Fluid Dynamics (CFD) and Coupled Codes; Nuclear Education, Public Acceptance and Related Issues (International Conference on Nuclear Engineering, Proceedings, ICONE; Vol. 8). American Society of Mechanical Engineers (ASME). https://doi.org/10.1115/ICONE25-66529
Tentner, Adrian ; Vegendla, Prasad ; Tomboulides, Ananias ; Obabko, Aleks ; Merzari, Elia ; Shaver, Dillon. / Modeling of two-phase boiling flow and critical heat flux with the NEK-2P CFD code. Computational Fluid Dynamics (CFD) and Coupled Codes; Nuclear Education, Public Acceptance and Related Issues. American Society of Mechanical Engineers (ASME), 2017. (International Conference on Nuclear Engineering, Proceedings, ICONE).
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Tentner, A, Vegendla, P, Tomboulides, A, Obabko, A, Merzari, E & Shaver, D 2017, Modeling of two-phase boiling flow and critical heat flux with the NEK-2P CFD code. in Computational Fluid Dynamics (CFD) and Coupled Codes; Nuclear Education, Public Acceptance and Related Issues. International Conference on Nuclear Engineering, Proceedings, ICONE, vol. 8, American Society of Mechanical Engineers (ASME), 2017 25th International Conference on Nuclear Engineering, ICONE 2017, Shanghai, China, 7/2/17. https://doi.org/10.1115/ICONE25-66529

Modeling of two-phase boiling flow and critical heat flux with the NEK-2P CFD code. / Tentner, Adrian; Vegendla, Prasad; Tomboulides, Ananias; Obabko, Aleks; Merzari, Elia; Shaver, Dillon.

Computational Fluid Dynamics (CFD) and Coupled Codes; Nuclear Education, Public Acceptance and Related Issues. American Society of Mechanical Engineers (ASME), 2017. (International Conference on Nuclear Engineering, Proceedings, ICONE; Vol. 8).

Research output: Chapter in Book/Report/Conference proceedingConference contribution

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Tentner A, Vegendla P, Tomboulides A, Obabko A, Merzari E, Shaver D. Modeling of two-phase boiling flow and critical heat flux with the NEK-2P CFD code. In Computational Fluid Dynamics (CFD) and Coupled Codes; Nuclear Education, Public Acceptance and Related Issues. American Society of Mechanical Engineers (ASME). 2017. (International Conference on Nuclear Engineering, Proceedings, ICONE). https://doi.org/10.1115/ICONE25-66529