Korean Journal of Air-Conditioning and Refrigeration Engineering (설비공학논문집)

The Society of Air-Conditioning and Refrigerating Engineers of Korea (대한설비공학회)
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Numerical Analysis of Flow Distribution inside a Fuel Assembly with Split-type Mixing Vanes for the Development of Regulatory Guideline on the Applicability of CFD Software

전산유체역학 소프트웨어 적용성에 관한 규제 지침 개발을 위한 분할 형태 혼합날개가 장착된 연료집합체 내부유동 분포 수치해석

  • Lee, Gong Hee (Nuclear Safety Research Department, Korea Institute of Nuclear Safety) ;
  • Cheong, Ae Ju (Nuclear Safety Research Department, Korea Institute of Nuclear Safety)
  • 이공희 (한국원자력안전기술원 원자력안전연구실) ;
  • 정애주 (한국원자력안전기술원 원자력안전연구실)
  • Received : 2017.06.30
  • Accepted : 2017.09.06
  • Published : 2017.10.10
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Abstract

In a PWR (Pressurized Water Reactor), the appropriate heat removal from the surface of fuel rod bundle is important for ensuring thermal margins and safety. Although many CFD (Computational Fluid Dynamics) software have been used to predict complex flows inside fuel assemblies with mixing vanes, there is no domestic regulatory guideline for the comprehensive evaluation of CFD software. Therefore, from the nuclear regulatory perspective, it is necessary to perform the systematic assessment and prepare the domestic regulatory guideline for checking whether valid CFD software is used for nuclear safety problems. In this study, to provide systematic evaluation and guidance on the applicability of CFD software to the domestic nuclear safety area, the results of the sensitivity analysis for the effect of the discretization scheme accuracy for the convection terms and turbulence models, which are main factors that contribute to the uncertainty in the calculation of the nuclear safety problems, on the prediction performance for the turbulent flow distribution inside the fuel assembly with split-type mixing vanes were explained.

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References

  1. Combustion Engineering, Inc., 1986, TORC Code : A Computer Code for Determining the Thermal Margin of a Reactor Core, CENPD-161-P-A(proprietary), CENPD-161-NP-A(non-proprietary).
  2. KEPCO Nuclear Fuel, 2013, THALES-Subchannel Analysis Code, KNF-TR-CDT-10006/NK/A Rev.0.
  3. Chang, S.-K., Kim, S., and Song, C.-H., 2014, Turbulent Mixing in a Rod Bundle with Vaned Spacer Grids : OECD/NEA-KAERI CFD Benchmark Exercise Test, Nuclear Engineering and Design, Vol. 279, pp. 19-36. https://doi.org/10.1016/j.nucengdes.2014.05.013
  4. Lee, J. R., Kim, J. W., and Song, C.-H., 2014, Synthesis of the Turbulent Mixing in a Rod Bundle with Vaned Spacer Grids Based on the OECD-KAERI CFD Benchmark Exercise, Nuclear Engineering and Design, Vol. 279, pp. 3-18. https://doi.org/10.1016/j.nucengdes.2014.03.008
  5. Smith, B. L., Song, C.-H., Chang S.-K., Lee, J. R., and Kim, J. W., 2013, Report of the OECD/NEA KAERI Rod Bundle CFD Benchmark Exercise, NEA/CSNI/R(2013)5, OECD NEA Committee on the Safety of Nuclear Installations.
  6. Menter, F., 2001, CFD Best Practice Guidelines for CFD Code Validation for Reactor Safety Applications, ECORA CONTRACT $N^{\circ}$ FIKS-CT-2001-00154.
  7. ANSYS Inc., ANSYS CFX, Version 14.0.
  8. Lee, G. H. and Cheong, A. J., 2015, CFD Analysis for the Turbulent Flow Distribution in a Fuel Assembly with the Split-type Mixing Vanes by Using the Advanced Scale-Resolving Turbulence Models, Applied Mechanics and Materials, Vol. 752-753, pp. 902-907. https://doi.org/10.4028/www.scientific.net/AMM.752-753.902
  9. Lee, G. H. and Cheong, A. J., 2016, Numerical Analysis of Flow Distribution Inside a Fuel Assembly with Split-Type Mixing Vanes, Trans. Korean Soc. Mech. Eng. B, Vol. 40, No. 5, pp. 329-337. https://doi.org/10.3795/KSME-B.2016.40.5.329