Nuclear Engineering and Technology

  • 제53권10호
  • /
  • Pages.3264-3274
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  • 2021
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  • 1738-5733(pISSN)
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  • 2234-358X(eISSN)
한국원자력학회 (Korean Nuclear Society)
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Numerical simulation on jet breakup in the fuel-coolant interaction using smoothed particle hydrodynamics

  • Choi, Hae Yoon (Department of Nuclear Engineering, Seoul National University) ;
  • Chae, Hoon (Department of Nuclear Engineering, Seoul National University) ;
  • Kim, Eung Soo (Department of Nuclear Engineering, Seoul National University)
  • 투고 : 2020.10.06
  • 심사 : 2021.04.20
  • 발행 : 2021.10.25
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초록

In a severe accident of light water reactor (LWR), molten core material (corium) can be released into the wet cavity, and a fuel-coolant interaction (FCI) can occur. The molten jet with high speed is broken and fragmented into small debris, which may cause a steam explosion or a molten core concrete interaction (MCCI). Since the premixing stage where the jet breakup occurs has a large impact on the severe accident progression, the understanding and evaluation of the jet breakup phenomenon are highly important. Therefore, in this study, the jet breakup simulations were performed using the Smoothed Particle Hydrodynamics (SPH) method which is a particle-based Lagrangian numerical method. For the multi-fluid system, the normalized density approach and improved surface tension model (CSF) were applied to the in-house SPH code (single GPU-based SOPHIA code) to improve the calculation accuracy at the interface of fluids. The jet breakup simulations were conducted in two cases: (1) jet breakup without structures, and (2) jet breakup with structures (control rod guide tubes). The penetration depth of the jet and jet breakup length were compared with those of the reference experiments, and these SPH simulation results are qualitatively and quantitatively consistent with the experiments.

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과제정보

This research was supported by the Nuclear Safety Research Program through the Korea Foundation Of Nuclear Safety (KoFONS) using the financial resource granted by the Nuclear Safety and Security Commission (NSSC) of the Republic of Korea. (No. 1903003). The Institute of Engineering Research at Seoul National University provided research facilities for this work.

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