Steady and unsteady calculations on thermal striping phenomena in triple-parallel jet

Y. Q. Yu, E. Merzari, J. W. Thomas, A. Obabko

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

2 Scopus citations

Abstract

The particular phenomena of thermal striping are encountered in liquid metal cooled fast reactors (LMFR), in which temperature fluctuation due to convective mixing between hot and cold fluids can lead to a possibility of crack initiation and propagation in the structure due to high cycle thermal fatigue. Using sodium experiments of parallel triple jets configuration performed by Japan Atomic Energy Agency (JAEA) as benchmark, numerical simulations were carried out to evaluate the temperature fluctuation characteristics in fluid and the transfer characteristics of temperature fluctuation from fluid to structure, which is important to assess the potential thermal fatigue damage. In this study, both steady (RANS) and unsteady (URANS, LES) calculations were applied to predict the temperature fluctuations of thermal striping. The verifications on mesh density and boundary conditions were carried out. The velocity, temperature and temperature fluctuation intensity distribution were compared with the experimental data. The steady calculation has limited success in predicting the thermal hydraulic characteristics of the thermal striping, highlighting the limitations of the RANS approach in unsteady heat transfer simulations. The unsteady results exhibited reasonably good agreement with experimental results for temperature fluctuation intensity, as well as the average temperature and velocity components at the measurement locations.

Original languageEnglish (US)
Title of host publicationInternational Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015
PublisherAmerican Nuclear Society
Pages1435-1447
Number of pages13
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
Volume2

Other

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

All Science Journal Classification (ASJC) codes

  • Instrumentation
  • Nuclear Energy and Engineering

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