Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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VALIDATION OF NUMERICAL METHODS TO CALCULATE BYPASS FLOW IN A PRISMATIC GAS-COOLED REACTOR CORE

  • Tak, Nam-Il (Korea Atomic Energy Research Institute) ;
  • Kim, Min-Hwan (Korea Atomic Energy Research Institute) ;
  • Lim, Hong-Sik (Korea Atomic Energy Research Institute) ;
  • Noh, Jae Man (Korea Atomic Energy Research Institute) ;
  • Drzewiecki, Timothy J. (Department of Nuclear Engineering and Radiological Sciences, University of Michigan) ;
  • Seker, Volkan (Department of Nuclear Engineering and Radiological Sciences, University of Michigan) ;
  • Downar, Thomas J. (Department of Nuclear Engineering and Radiological Sciences, University of Michigan) ;
  • Kelly, Joseph (US Nuclear Regulatory Commission)
  • Received : 2013.09.24
  • Accepted : 2013.10.02
  • Published : 2013.11.25
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Abstract

For thermo-fluid and safety analyses of a High Temperature Gas-cooled Reactor (HTGR), intensive efforts are in progress in the developments of the GAMMA+ code of Korea Atomic Energy Research Institute (KAERI) and the AGREE code of the University of Michigan (U of M). One of the important requirements for GAMMA+ and AGREE is an accurate modeling capability of a bypass flow in a prismatic core. Recently, a series of air experiments were performed at Seoul National University (SNU) in order to understand bypass flow behavior and generate an experimental database for the validation of computer codes. The main objective of the present work is to validate the GAMMA+ and AGREE codes using the experimental data published by SNU. The numerical results of the two codes were compared with the measured data. A good agreement was found between the calculations and the measurement. It was concluded that GAMMA+ and AGREE can reliably simulate the bypass flow behavior in a prismatic core.

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References

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