Experiment on Coolability through External Reactor Vessel Cooling according to RPV Insulation Design

국내원전 단열재 설계특성에 따른 외벽냉각 효과검증 실험

  • 강경호 (한국원자력연구소 열수력안전연구부) ;
  • 박래준 (한국원자력연구소 열수력안전연구부) ;
  • 김상백 (한국원자력연구소 열수력안전연구부)
  • Published : 2003.04.23

Abstract

LAVA-ERVC experiments have been performed to investigate the effect of insulation design features on the coolability in case of the external reactor vessel cooling (ERVC). All the 4 tests have been performed using Alumina iron thermite melt as a corium simulant. Due to the limited steam venting through the insulation, steam binding occurred inside the annulus in the KSNP case simulation. On the contrary, in the tests which were performed for simulating the APR1400 insulation design, sufficient water ingression and steam venting through the insulation lead to effective cool down of the vessel characterized by nucleate boiling. It could be found from the experimental results that modification of the insulation design allowing sufficient ventilation could increase the positive effects of the external reactor vessel cooling.

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