Nuclear Engineering and Technology

  • 제53권8호
  • /
  • Pages.2477-2487
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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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Integral effect test for steam line break with coupling reactor coolant system and containment using ATLAS-CUBE facility

  • Bae, Byoung-Uhn (Innovative System Safety Research Division, Korea Atomic Energy Research Institute) ;
  • Lee, Jae Bong (Innovative System Safety Research Division, Korea Atomic Energy Research Institute) ;
  • Park, Yu-Sun (Innovative System Safety Research Division, Korea Atomic Energy Research Institute) ;
  • Kim, Jongrok (Innovative System Safety Research Division, Korea Atomic Energy Research Institute) ;
  • Kang, Kyoung-Ho (Innovative System Safety Research Division, Korea Atomic Energy Research Institute)
  • 투고 : 2020.11.25
  • 심사 : 2021.02.23
  • 발행 : 2021.08.25
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초록

To improve safety analysis technology for a nuclear reactor containment considering an interaction between a reactor coolant system (RCS) and containment, this study aims at an experimental investigation on the integrated simulation of the RCS and containment, with an integral effect test facility, ATLAS-CUBE. For a realistic simulation of a pressure and temperature (P/T) transient, the containment simulation vessel was designed to preserve a volumetric scale equivalently to the RCS volume scale of ATLAS. Three test cases for a steam line break (SLB) transient were conducted with variation of the initial condition of the passive heat sink or the steam flow direction. The test results indicated a stratified behavior of the steam-gas mixture in the containment following a high-temperature steam injection in prior to the spray injection. The test case with a reduced heat transfer on the passive heat sink showed a faster increase of the P/T inside the containment. The effect of the steam flow direction was also investigated with respect to a multi-dimensional distribution of the local heat transfer on the passive heat sink. The integral effect test data obtained in this study will contribute to validating the evaluation methodology for mass and energy (M/E) and P/T transient of the containment.

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과제정보

The authors are grateful to the Ministry of Science and ICT of Korea for their financial and technical support for the research project (NRF-2017M2A8A4015028) and to the Korea Hydro & Nuclear Power (KHNP) for their financial support on this project (Contract No. L16S102000).

참고문헌

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