Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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HEAT REMOVAL TEST USING A HALF SCALE STORAGE CASK

  • Bang, K.S. (Korea Atomic Energy Research Institute) ;
  • Lee, J.C. (Korea Atomic Energy Research Institute) ;
  • Seo, K.S. (Korea Atomic Energy Research Institute) ;
  • Cho, C.H. (Nuclear Engineering & Technology Institute) ;
  • Lee, S.J. (Nuclear Engineering & Technology Institute) ;
  • Kim, J.M. (Nuclear Engineering & Technology Institute)
  • Published : 2007.04.30
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Abstract

Spent nuclear fuel generated at nuclear power plants must be safely stored during interim storage periods. A dry storage cask to safely store the spent nuclear fuel should be able to adequately emit the decay heat from the spent nuclear fuel. Therefore, heat removal tests using a half scale dry storage cask have been performed to estimate the heat transfer characteristics of a dry storage cask under normal, off-normal, and accident conditions. In the normal condition, the heat transfer rate to an ambient atmosphere by convective air through a passive heat removal system reached 83%. Accordingly, the passive heat removal system is designed well and works adequately. In the off-normal condition, the influence of a half blockage in the inlet on the temperature appears minimal. In the accident condition, the temperature rose for 12 hours after the accident, but the temperature rise steadied after 36 hours.

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References

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