한국시뮬레이션학회:학술대회논문집 (Proceedings of the Korea Society for Simulation Conference)

한국시뮬레이션학회 (The Korea Society for Simulation)
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최적 계통분석 코드를 이용한 웨스팅하우스형 원자력발전소 시뮬레이터용 핵 증기 공급 계통 열수력 프로그램 개발

Development of An Nuclear Steam Supply System Thermal-Hydraulic Program for the Westinghouse Type Nuclear Power Plant Simulator Using A Best-Estimate Code

  • 서재승 (㈜미래와 도전) ;
  • 전규동 (한양대학교 시스템응용공학부) ;
  • 이명수 (한국전력공사 전력연구원) ;
  • 이용관 (한국전력공사 전력연구원)
  • 발행 : 2004.05.01
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초록

KEPRI has developed an Nuclear Steam Supply System(NSSS) thermal-hydraulic simulation program (called ARTS-KORIl) based on the best-estimate system code, RETRAN, as a part of the development project for the KORI unit 1 nuclear power plant simulator. To develop the RETRAN code as an NSSS T/H engine for the simulator, a number of code modifications, such as simplifications and removing of discontinuities of the physical correlations, were made to satisfy the simulator requirements of robustness and real time calculation capability Some simplified models and a backup system were also developed to simulate some transients that cannot be efficiently calculated by the RETRAN part of ARTS-KORIl.

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