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Verification of SPACE Code with MSGTR-PAFS Accident Experiment

증기발생기 전열관 다중파단-피동보조급수냉각계통 사고 실험 기반 안전해석코드 SPACE 검증

  • Nam, Kyung Ho (Central Research Institute, Korea Hydro & Nuclear Power Co., Ltd) ;
  • Kim, Tae Woo (Central Research Institute, Korea Hydro & Nuclear Power Co., Ltd)
  • 남경호 (한국수력원자력(주) 중앙연구원) ;
  • 김태우 (한국수력원자력(주) 중앙연구원)
  • Received : 2020.06.25
  • Accepted : 2020.08.03
  • Published : 2020.08.31

Abstract

The Korean nuclear industry developed the SPACE (Safety and Performance Analysis Code for nuclear power plants) code and this code adpots two-phase flows, two-fluid, three-field models which are comprised of gas, continuous liquid and droplet fields and has a capability to simulate three-dimensional model. According to the revised law by the Nuclear Safety and Security Commission (NSSC) in Korea, the multiple failure accidents that must be considered for accident management plan of nuclear power plant was determined based on the lessons learned from the Fukushima accident. Generally, to improve the reliability of the calculation results of a safety analysis code, verification work for separate and integral effect experiments is required. In this reason, the goal of this work is to verify calculation capability of SPACE code for multiple failure accident. For this purpose, it was selected the experiment which was conducted to simulate a Multiple Steam Generator Tube Rupture(MSGTR) accident with Passive Auxiliary Feedwater System(PAFS) operation by Korea Atomic Energy Research Institute (KAERI) and focused that the comparison between the experiment results and code calculation results to verify the performance of the SPACE code. The MSGR accident has a unique feature of the penetration of the barrier between the Reactor Coolant System (RCS) and the secondary system resulting from multiple failure of steam generator U-tubes. The PAFS is one of the advanced safety features with passive cooling system to replace a conventional active auxiliary feedwater system. This system is passively capable of condensing steam generated in steam generator and feeding the condensed water to the steam generator by gravity. As the results of overall system transient response using SPACE code showed similar trends with the experimental results such as the system pressure, mass flow rate, and collapsed water level in component. In conclusion, it could be concluded that the SPACE code has sufficient capability to simulate a MSGTR accident.

Keywords

References

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