CFD modeling of supercritical water heat transfer in a vertical bare tube upward flow

Vladimir Agranat, Michael Malin, Igor Pioro, Rand Abdullah, Valeriy Afanasievich Perminov

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

5 Citations (Scopus)

Abstract

A customized Computational Fluid Dynamics (CFD) model of supercritical water (SCW) heat transfer in a vertical tube upward flow is developed and partially validated using experimental data obtained under the operating conditions typical for SCW cooled reactors (SCWRs): at a pressure of 24 MPa, an inner tube diameter of 10 mm, an inlet temperature of 320 or 350 °C and a heated tube length of 4 m. The three values of mass flux (500, 1000 and 1500 kg/m2s) and various values of wall heat flux (from 141 to 729 kW/m2) are considered. Physical properties of SCW are calculated by using the REFPROP software from National Institute of Standards and Technology (NIST). The model has been incorporated into the commercial general-purpose CFD software, PHOENICS. Various turbulence models and numerical grid settings are tested. The study has demonstrated a good agreement between the CFD predictions and the experimental data on the inside tube wall temperature and heat transfer coefficient with use of a two-layer low-Reynolds-number k-ε turbulence model. However, a further model development is required under the conditions of significant effects of buoyancy force on heat transfer characteristics (the conditions of low values of mass flux and high values of wall heat flux). Practical recommendations are made regarding potential model applications in 3D analyses of SCWRs.

Original languageEnglish
Title of host publicationICONE 2015 - 23rd International Conference on Nuclear Engineering: Nuclear Power - Reliable Global Energy
PublisherAmerican Society of Mechanical Engineers(ASME)
Volume2015-January
Publication statusPublished - 2015
Event23rd International Conference on Nuclear Engineering: Nuclear Power - Reliable Global Energy, ICONE 2015 - Chiba, Japan
Duration: 17 May 201521 May 2015

Conference

Conference23rd International Conference on Nuclear Engineering: Nuclear Power - Reliable Global Energy, ICONE 2015
CountryJapan
CityChiba
Period17.5.1521.5.15

Keywords

  • Computational Fluid Dynamics
  • Heat transfer
  • PHOENICS software
  • Supercritical Water
  • Upward flow
  • Validation
  • Vertical tube

ASJC Scopus subject areas

  • Nuclear Energy and Engineering

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  • Cite this

    Agranat, V., Malin, M., Pioro, I., Abdullah, R., & Perminov, V. A. (2015). CFD modeling of supercritical water heat transfer in a vertical bare tube upward flow. In ICONE 2015 - 23rd International Conference on Nuclear Engineering: Nuclear Power - Reliable Global Energy (Vol. 2015-January). American Society of Mechanical Engineers(ASME).