Nuclear Engineering and Technology

  • 제56권11호
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  • Pages.4859-4867
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  • 2024
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  • 1738-5733(pISSN)
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  • 2234-358X(eISSN)
한국원자력학회 (Korean Nuclear Society)
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Performance evaluation of the SMART passive safety injection system against the SBLOCA scenario with the SMART-ITL facility

  • Hyun-Sik Park (Reactor System Safety Research Division, Korea Atomic Energy Research Institute) ;
  • Hwang Bae (Reactor System Safety Research Division, Korea Atomic Energy Research Institute) ;
  • Sung-Uk Ryu (Reactor System Safety Research Division, Korea Atomic Energy Research Institute) ;
  • Byong-Guk Jeon (Reactor System Safety Research Division, Korea Atomic Energy Research Institute) ;
  • Jin-Hwa Yang (Reactor System Safety Research Division, Korea Atomic Energy Research Institute) ;
  • Yoon-Gon Bang (Reactor System Safety Research Division, Korea Atomic Energy Research Institute) ;
  • Sung-Jae Yi (Reactor System Safety Research Division, Korea Atomic Energy Research Institute)
  • 투고 : 2024.05.03
  • 심사 : 2024.06.29
  • 발행 : 2024.11.25
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초록

A set of system performance tests has been performed and the thermal-hydraulic behaviors were investigated for the passive safety injection system (PSIS) of the SMART design. Major thermal-hydraulic characteristics of core cooling in reactor coolant system and safety injection (SI) in PSIS were investigated using the SMART-ITL. The parametric effects of break size, break location and train number on the PSIS performance were discussed with the relevant SMART-ITL data. Compared with the 2.0 inch SI line break test, the 0.4 inch SI line break test has a milder change of system parameters. The pressure is reduced more quickly, the decrease of water level is slower and the break mass flow rate is higher during the pressurizer safety valve line break than during the SI line break. Major thermal-hydraulic parameters were compared among single, two and full train operation of the PSIS focusing on the effect of train number. It was shown that multiple trains of CMT and SIT were operated independently and the reactor vessel (RV) inventory increased proportionally with the addition of each train. Sufficient SI water was injected into the RV in a passive manner to cool down the reactor core efficiently during the full train test.

키워드

과제정보

This work was supported by the SMART100 Standard Design Approval Project funded by KAERI, KHNP, and K.A.CARE.

참고문헌

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