Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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Comparison of three small-break loss-of-coolant accident tests with different break locations using the system-integrated modular advanced reactor-integral test loop facility to estimate the safety of the smart design

  • Bae, Hwang (SMART Reactor Design Division, Korea Atomic Energy Research Institute) ;
  • Kim, Dong Eok (Department of Precision Mechanical Engineering, Kyungpook National University) ;
  • Ryu, Sung-Uk (Thermal Hydraulics Safety Research Division, Korea Atomic Energy Research Institute) ;
  • Yi, Sung-Jae (Thermal Hydraulics Safety Research Division, Korea Atomic Energy Research Institute) ;
  • Park, Hyun-Sik (Thermal Hydraulics Safety Research Division, Korea Atomic Energy Research Institute)
  • Received : 2016.10.13
  • Accepted : 2017.04.07
  • Published : 2017.08.25
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Abstract

Three small-break loss-of-coolant accident (SBLOCA) tests with safety injection pumps were carried out using the integral-effect test loop for SMART (System-integrated Modular Advanced ReacTor), i.e., the SMART-ITL facility. The types of break are a safety injection system line break, shutdown cooling system line break, and pressurizer safety valve line break. The thermal-hydraulic phenomena show a traditional behavior to decrease the temperature and pressure whereas the local phenomena are slightly different during the early stage of the transient after a break simulation. A safety injection using a high-pressure pump effectively cools down and recovers the inventory of a reactor coolant system. The global trends show reproducible results for an SBLOCA scenario with three different break locations. It was confirmed that the safety injection system is robustly safe enough to protect from a core uncovery.

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