Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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Numerical simulation of complex hexagonal structures to predict drop behavior under submerged and fluid flow conditions

  • Yoon, K.H. (Korea Atomic Energy Research Institute) ;
  • Lee, H.S. (Korea Atomic Energy Research Institute) ;
  • Oh, S.H. (ELSOLTEC Inc.) ;
  • Choi, C.R. (ELSOLTEC Inc.)
  • Received : 2018.04.20
  • Accepted : 2018.08.17
  • Published : 2019.02.25
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Abstract

This study simulated a control rod assembly (CRA), which is a part of reactor shutdown systems, in immersed and fluid flow conditions. The CRA was inserted into the reactor core within a predetermined time limit under normal and abnormal operating conditions, and the CRA (which consists of complex geometric shapes) drop behavior is numerically modeled for simulation. A full-scale prototype CRA drop test is established under room temperature and water-fluid conditions for verification and validation. This paper describes the details of the numerical modeling and analysis results of the several conditions. Results from the developed numerical simulation code are compared with the test results to verify the numerical model and developed computer code. The developed code is in very good agreement with the test results and this numerical analysis model and method may replace the experimental and CFD method to predict the drop behavior of CRA.

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References

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