Advances in modeling critical heat flux in LWR boiling flows 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

2 Scopus citations

Abstract

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.

Original languageEnglish (US)
Title of host publicationComputational Fluid Dynamics (CFD); Nuclear Education and Public Acceptance
PublisherAmerican Society of Mechanical Engineers (ASME)
ISBN (Print)9784888982566
DOIs
StatePublished - Jan 1 2018
Event2018 26th International Conference on Nuclear Engineering, ICONE 2018 - London, United Kingdom
Duration: Jul 22 2018Jul 26 2018

Publication series

NameInternational Conference on Nuclear Engineering, Proceedings, ICONE
Volume8

Other

Other2018 26th International Conference on Nuclear Engineering, ICONE 2018
CountryUnited Kingdom
CityLondon
Period7/22/187/26/18

All Science Journal Classification (ASJC) codes

  • Nuclear Energy and Engineering

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