Journal of computational fluids engineering (한국전산유체공학회지)

Korean Society of Computational Fluids Engineering (한국전산유체공학회)
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LARGE EDDY SIMULATION OF THERMAL STRIPING IN THE UPPER PLENUM OF FAST REACTOR

대와동모사법을 사용한 고속로 상부플레넘에서의 thermal sriping 해석

  • Choi, S.K. (Fast Reactor Design Division, Korea Atomic Energy Research Institute) ;
  • Han, J.W. (Fast Reactor Design Division, Korea Atomic Energy Research Institute) ;
  • Kim, D. (Fast Reactor Design Division, Korea Atomic Energy Research Institute) ;
  • Lee, T.H. (Fast Reactor Design Division, Korea Atomic Energy Research Institute)
  • 최석기 (한국원자력연구원 고속로설계부) ;
  • 한지웅 (한국원자력연구원 고속로설계부) ;
  • 김대희 (한국원자력연구원 고속로설계부) ;
  • 이태호 (한국원자력연구원 고속로설계부)
  • Received : 2014.09.24
  • Accepted : 2014.12.05
  • Published : 2014.12.31
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Abstract

A computational study of a thermal striping in the upper plenum of PGSFR(Prototype Generation-IV Sodium-cooled Fast Reactor) being developed at the KAERI(Korea Atomic Energy Research Institute) is presented. The LES(Large Eddy Simulation) approach is employed for the simulation of thermal striping in the upper plenum of the PGSFR. The LES is performed using the WALE (Wall-Adapting Local Eddy-viscosity) model. More than 19.7 million unstructured elements are generated in upper plenum region of the PGSFR using the CFX-Mesh commercial code. The time-averaged velocity components and temperature field in the complicated upper plenum of the PGSFR are presented. The time history of temperature fluctuation at the eight locations of solid walls of UIS(Upper Internal Structure) and IHX(Intermediate Heat eXchanger) are additionally stored. It has been confirmed that the most vulnerable regions to thermal striping are the first plate of UIS. From the temporal variation of temperature at the solid walls, it was possible to find the locations where the thermal stress is large and need to assess whether the solid structures can endure the thermal stress during the reactor life time.

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References

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