Nuclear Engineering and Technology

  • 제55권4호
  • /
  • Pages.1571-1584
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  • 2023
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  • 1738-5733(pISSN)
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  • 2234-358X(eISSN)
한국원자력학회 (Korean Nuclear Society)
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Numerical study to reproduce a real cable tray fire event in a nuclear power plant

  • Jaiho Lee (Department of Reactor System Evaluation, Korea Institute of Nuclear Safety (KINS)) ;
  • Byeongjun Kim (Department of Mechanical Engineering, Chungnam National University) ;
  • Yong Hun Jung (Korea Atomic Energy Research Institute (KAERI)) ;
  • Sangkyu Lee (Department of Reactor System Evaluation, Korea Institute of Nuclear Safety (KINS)) ;
  • Weon Gyu Shin (Department of Mechanical Engineering, Chungnam National University)
  • 투고 : 2022.06.20
  • 심사 : 2023.02.04
  • 발행 : 2023.04.25
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초록

In this study, a numerical analysis was performed as part of an international joint research project to reproduce a real cable tray fire that occurred in the heater bay area of the turbine building of a nuclear power plant. A sensitivity analysis was performed on various input parameters to derive results consistent with the sprinkler activation time obtained from the fire event analysis. For all sensitive parameters, the normalized sprinkler activation time correlated well with the power function of the normalized sprinkler height. A correlation equation was developed to identify the sprinkler activation time at any location when determining the slope or fire growth rate under the conditions assuming a linear or t-squared heat release rate (HRR) time curve. Various cable fire growth assumptions were used to determine which assumption was better to provide the prediction coincident with the information given from the fire event analysis in terms of the sprinkler activation time and total energy generated from cables damaged by fire. In the comprehensive analysis of all the sensitive parameters, the standard deviation of the input parameters increased as the sprinkler height decreased. Within the range of the sensitivity parameter values given in this study, when considering all sprinkler heights, the standard deviation of the cable model change was the largest and that of the overhang position change was the smallest.

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과제정보

This work was supported by the Nuclear Safety Research Program through the Korea Foundation of Nuclear Safety (KoFONS) using the financial resources granted by the Nuclear Safety and Security Commission (NSSC) of the Republic of Korea. (NO.1705002, and NO.2106006).

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