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

한국시뮬레이션학회 (The Korea Society for Simulation)
권호 표지

최적 계통분석 코드를 이용한 웨스팅하우스형 원자력발전소 시뮬레이터용 핵 증기 공급 계통 열수력 프로그램 독자평가 및 시험

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

  • 서인용 (한국전력공사 전력연구원) ;
  • 이명수 (한국전력공사 전력연구원) ;
  • 이용관 (한국전력공사 전력연구원) ;
  • 서재승 (㈜미래와 도전) ;
  • 권순일 (고리원자력교육원 훈련센타)
  • 발행 : 2004.05.01
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초록

KEPRI has developed an Nuclear Steam Supply System(NSSS) thermal-hydraulics simulation program (called ARTS-KORI), based on the best-estimate system code, RETRAN, as a part of the development project for the KORI unit 1 Nuclear Power Plant Simulator. A number of code modifications, such as simplifications and removing of discontinuities of the physical correlations, were made in order to change the RETRAN code as an nuclear Steam Supply System thermal-hydraulics engine in the simulator. Some simplified models and a backup system were also developed. This paper briefly presents the results of non-integrated standalone test of ARTS-KORI.

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