Computational fluid dynamics modeling of two-phase boiling flow and critical heat flux

Adrian Tentner, Elia Merzari, Prasad Vegendla

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

7 Scopus citations

Abstract

This paper presents recent advances in the modeling of two-phase boiling flow and critical heat flux that have been implemented in the Extended Boiling Framework (EBF) [1, 2, 3]. The EBF code was developed as a customized module built on the foundation of the commercial Computational Fluid Dynamics (CFD) code STAR-CD, which provides general twophase flow modeling capabilities, for the detailed analysis of the two-phase flow and heat transfer phenomena that occur in Boiling Water Reactor (BWR) fuel assemblies. These phenomena include coolant phase changes and multiple flow regimes that directly influence the coolant interaction with the fuel pins and, ultimately, the reactor performance. An effort to expand the EBF two-phase models and to explore their applicability to other CFD codes is currently underway. The paper presents results of recent CFD analyses of Critical Heat Flux (CHF) experiments that have measured the axial distribution of wall temperature in two-phase upward flow in a vertical channel with a heated wall. The experiments were designed to produce the onset of CHF in the upper half of the heated channel. The simulated axial distribution of wall temperature is compared with experimental data, illustrating the ability of the extended EBF model to capture the onset of CHF for a wide range of thermal-hydraulic conditions relevant for BWRs. The paper concludes with a discussion of results and plans for future work.

Original languageEnglish (US)
Title of host publicationRadiation Protection and Nuclear Technology Applications; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Reactor Physics and Transport Theory
PublisherAmerican Society of Mechanical Engineers (ASME)
ISBN (Electronic)9780791845943
DOIs
StatePublished - Jan 1 2014
Event2014 22nd International Conference on Nuclear Engineering, ICONE 2014 - Prague, Czech Republic
Duration: Jul 7 2014Jul 11 2014

Publication series

NameInternational Conference on Nuclear Engineering, Proceedings, ICONE
Volume4

Conference

Conference2014 22nd International Conference on Nuclear Engineering, ICONE 2014
CountryCzech Republic
CityPrague
Period7/7/147/11/14

All Science Journal Classification (ASJC) codes

  • Nuclear Energy and Engineering

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    Tentner, A., Merzari, E., & Vegendla, P. (2014). Computational fluid dynamics modeling of two-phase boiling flow and critical heat flux. In Radiation Protection and Nuclear Technology Applications; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Reactor Physics and Transport Theory (International Conference on Nuclear Engineering, Proceedings, ICONE; Vol. 4). American Society of Mechanical Engineers (ASME). https://doi.org/10.1115/ICONE22-30844