Modeling of two-phase flow in a BWR fuel assembly with a highly-scalable CFD code

Adrian Tentner, Prasad Vegendla, Aleks Obabko, Ananias Tomboulides, Paul Fischer, Oana Marin, Elia Merzari

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

10 Scopus citations

Abstract

A project is underway to develop an advanced two-phase flow modeling capability for the highly-scalable high-performance CFD code NEK5000 [1]. The goal of the project is to develop a new two-phase version of the NEK5000 code, named NEK-2P, to simulate the two-phase flow and heat transfer phenomena that occur in a Boiling Water Reactor (BWR) fuel bundle under various operating conditions. The NEK-2P two-phase flow models will follow the approach used for the Extended Boiling Framework [2, 3, 4] previously developed at Argonne, but will include more fundamental physical models of boiling phenomena and advanced numerical algorithms for improved computational accuracy, robustness, and computational speed. The NEK-2P code is being developed on the foundation of the NEK5000 CFD Code developed at Argonne which provides general high-fidelity single-phase flow modeling capabilities. The paper describes the model development strategy which has been adopted by the development team for the simulation of two-phase boiling flow phenomena typical for a BWR fuel bundle. This strategy includes the extension of NEK5000 solver to allow modeling of two-phase boiling flows, and the implementation of an Advanced Boiling Framework (ABF) using local inter-phase surface topology maps and topology- specific phenomenological models. Results of initial analyses of selected experiments focused on boiling flow in a pipe with heated wall are presented.

Original languageEnglish (US)
Title of host publicationInternational Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015
PublisherAmerican Nuclear Society
Pages1966-1979
Number of pages14
ISBN (Electronic)9781510811843
StatePublished - Jan 1 2015
Event16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2015 - Chicago, United States
Duration: Aug 30 2015Sep 4 2015

Publication series

NameInternational Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015
Volume3

Other

Other16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2015
CountryUnited States
CityChicago
Period8/30/159/4/15

All Science Journal Classification (ASJC) codes

  • Instrumentation
  • Nuclear Energy and Engineering

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  • Cite this

    Tentner, A., Vegendla, P., Obabko, A., Tomboulides, A., Fischer, P., Marin, O., & Merzari, E. (2015). Modeling of two-phase flow in a BWR fuel assembly with a highly-scalable CFD code. In International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015 (pp. 1966-1979). (International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015; Vol. 3). American Nuclear Society.