Journal of Energy Engineering (에너지공학)

The Korean Society for Energy (한국에너지학회)
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Preliminary Analysis of the Thermal-Hydraulic Performance of a Passive Containment Cooling System using the MARS-KS1.3 Code

MARS-KS1.3을 이용한 피동원자로건물냉각계통 열수력 성능 예비분석

  • Bae, Sung Hwan (School of Mechanical Engineering, Pusan National University) ;
  • Ha, Tae Wook (School of Mechanical Engineering, Pusan National University) ;
  • Jeong, Jae Jun (School of Mechanical Engineering, Pusan National University) ;
  • Yun, Byong Jo (School of Mechanical Engineering, Pusan National University) ;
  • Jerng, Dong Wook (School of Energy System, Chung-Ang University) ;
  • Kim, Han Gon (Central Research Institute, Korea Hydro and Nuclear Power Co.)
  • 배성환 (부산대학교 기계공학부) ;
  • 하태욱 (부산대학교 기계공학부) ;
  • 정재준 (부산대학교 기계공학부) ;
  • 윤병조 (부산대학교 기계공학부) ;
  • 정동욱 (중앙대학교 에너지시스템공학부) ;
  • 김한곤 (한국수력원자력 중앙연구원)
  • Received : 2015.06.16
  • Accepted : 2015.09.18
  • Published : 2015.09.30
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Abstract

A passive containment cooling system has been designed to remove the heat inside a containment during accidents without external power supply. In this work, the PCCS was introduced in the APR1400 plant to replace the containment spray system and, then, the thermal-hydraulic performance of the PCCS was analyzed using the system thermal-hydraulic computer code, MARS. A double-ended cold-leg break accident, which is known to induce the maximum pressure in the containment, is simulated, where the thermal hydraulics of the PCCS, the reactor coolant system, and the containment are simultaneously simulated. The results of the calculations showed that the PCCS can replace the existing spray system and that the containment building and its internal structure also play a very important role for the heat removal during the accident. Some sensitivity calculations were carried out to evaluate the model uncertainty and the effects of design parameters. The limitations of the PCCS are also discussed.

피동원자로건물냉각계통(Passive Containment Cooling System; PCCS)은 전원 공급 없이도 원자로건물 내부의 열을 제거하여 그 건전성을 유지시키기 위한 안전설비이다. 본 연구에서는 현재 연구중인 PCCS를 1400 MWe 가압경수형 원전(APR1400)에 설치하는 경우 PCCS 성능을 분석하였다. 분석도구로 계통열수력분석코드 MARS-KS1.3을 사용하였다. PCCS의 성능분석을 위해 APR 1400 표준안전성분석 보고서를 참고하여 원자로건물 내부의 최대압력을 유발하는 사고 시나리오인 저온관 양단 파단사고를 모의하였다. 이 계산에서는 PCCS, 원자로냉각계통 및 원자로건물의 열수력을 동시에 모의하였다. 계산결과를 통해 기존의 원자로건물 살수계통을 대체하여 PCCS가 원자로건물의 건전성을 유지시킬 수 있음을 확인하였다. 또한 PCCS의 성능에 영향을 줄 수 있는 여러 인자를 변경해가며 민감도 분석을 수행하였고 PCCS의 문제점도 확인하였다.

Keywords

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