• 제목/요약/키워드: RETRAN

검색결과 49건 처리시간 0.045초

Determination of Optimum Pressurizer Level for Kori Unit 1

  • Song, Dong-Soo;Lee, Chang-Sup;Lee, Jae-Yong;Kim, Yo-Han;Lee, Dong-Hyuk
    • 한국원자력학회:학술대회논문집
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    • 한국원자력학회 1997년도 추계학술발표회논문집(1)
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    • pp.437-442
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    • 1997

  • To determine the optimum pressurizer water level during normal operation for Kori unit 1, performance and safety analysis are peformed. The methodology is developed by evaluating "decrease in secondary heat removal" events such as Loss of Normal Feedwater accident. To demonstrate optimum pressurizer level setpoint, RETRAN-03 code is used for performance analysis. Analysis results of RETRAN following reactor trip are compared with the actual plant data to justify RETRAN code modelling, The results of performance and safety analyses show that the newly established level setpoints not only improve the performance of pressurizer during transient including reactor trip but also meet the design bases of the pressurizer volume and pressure. pressure.

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Development of Main Steam Line Break Mass and Energy Release Analysis with RETRAN-3D Code

  • Park, Young-Chan;Kim, Yoo
    • 에너지공학
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    • 제12권2호
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    • pp.93-100
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    • 2003

  • An estimation methodology of the mass and energy (M/E) release due to the main steam line break (MSLB) has been developed with the RETRAN-3D code. In the case of equipment qualification (EQ), the over-estimated temperature would exceed the design limits of some cables or valves. In order to have a more flexible EQ profiles from the MSLB M/E release, the methodology with the best-estimated code was used. The major conditions affecting the MSLB M/E were found to be the initial SG level, heat transfer between primary and secondary sides, power level, operable protection system, main or auxiliary feedwater availability, and break conditions. The RETRAN-3D models were developed for the Kori unit 1 (KRN-1) which is typical two loop Westinghouse (WH) designed plant. Particularly, a detailed model of the steam generators was developed to estimate a more realistic two-phase heat transfer effect of the steam flow. After the modeling, the methodology has been developed through the sensitivity analyses. The M/E release data generated from the analyses have been used as the input to the inside containment pressure and temperature (P/T) analysis. According to the results at the point of view containment P/T, the Kori unit 1 can have more margin of 5∼15 ㎪ in pressure and 8∼15$^{\circ}C$ in temperature.

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웨스팅하우스형 원자력발전소 가압기 방출 탱크의 실시간 시뮬레이션을 위한 전문모델 개발 (Development of a Dedicated Model for a Real-Time Simulation of the Pressurizer Relief Tank of the Westinghouse Type Nuclear Power Plant)

  • 서재승;전규동
    • 한국시뮬레이션학회논문지
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    • 제13권2호
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    • pp.13-21
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    • 2004

  • The thermal-hydraulic model ARTS which was based on the RETRAN-3D code adopted in the domestic full-scope power plant simulator which was provided in 1998 by KEPRI. Since ARTS is a generalized code to model the components with control volumes, the smaller time-step size should be used even if converged solution could not get in a single volume. Therefore, dedicated models which do not force to reduce the time-step size are sometimes more suitable in terms of a real-time calculation and robustness. In the case of PRT(Pressurizer Relief Tank) model, it is consist of subcooled water in bottom and non-condensable gas in top. The sparger merged under subcooled water enhances condensation. The complicated thermal-hydraulic phenomena such as condensation, phase separation with existence of non-condensable gas makes difficult to simulate. Therefore, the PRT volume can limit the time-step size if we model it with a general control volume. To prevent the time-step size reduction due to convergence failure for simulating this component, we developed a dedicated model for PRT. The dedicated model was expected to provide substantially more accurate predictions in the analysis of the system transients. The results were resonable in terms of accuracy, real-time simulation, robustness and education of operators, complying with the ANSI/ANS-3.5-1998 simulator software performance criteria and RETRAN-3D results.

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KINS W/H형 원전분석기 MMI 개발 (The development of MMI for KINS NPA)

  • 서인용
    • 한국시뮬레이션학회:학술대회논문집
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    • 한국시뮬레이션학회 2004년도 춘계학술대회 논문집
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    • pp.89-93
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    • 2004

  • 본 MMI를 통해 개발된 웨스팅하우스 950 Mwe 최적 NPA는 기존의 단순한 Point Kinetics 모델이 아닌 정교한 3D 실시간 노심모델과 RETRAN 코드를 기반으로 하는 실시간 NSSS 열수력 모델(ARTS)이 통합된 모델을 갖추었으며, 해당형식 발전소(Westinghouse 3 Loop PWR Plant)의 여러 가지 과도사고를 실시간으로 정상, 비정상, 비상운전 모의할 수 있도록 개발되었다. 이 NPA는 기존의 유닉스 환경이 아닌 일반 범용 PC 서버와 윈도우즈 환경(Operating System)이라는 개방형 서버-클라이언트 구조를 채택하여 저렴하고 실용적인 시스템을 추구하였다. 다양한 색상 표현이 가능한 GUI 툴을 이용하여 노심 내부의 3D 열중성자 속 분포등 사용자가 직관적으로 알 수 있는 쉬운 구성의 클라이언트 제어 시스템을 개발, 연계하여 사용자의 편의성을 도모하였다.

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WH형 950MWe 원전 운전최적분석기 개발 (Development of Westinghouse 950 MWe-type NPA)

  • 홍진혁
    • 한국에너지공학회:학술대회논문집
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    • 한국에너지공학회 2003년도 춘계 학술발표회 논문집
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    • pp.473-483
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    • 2003

  • 본 논문은 안전해석 등에 사용되는 RETRAN-3D 등 최적해석 코드를 기반으로 하면서도 복잡한 하드웨어 없이 간편한 GUI (Graphic User Interface)를 이용하여 광범위한 발전소 과도상태를 해석하기 위한 다양한 기능을 통해 시뮬레이션 조작을 쉽게 할 수 있는 웨스팅하우스형 950MW급 최적 원전운전분석기 (Nuclear Plant Analyzer)를 다루고자 한다. WH형 950MW 원전 운전최적분석기는 기존의 단순한 Point Kinetics 모델이 아닌 정교한 3D 실시간 노심모델과 RETRAN 코드를 기반으로 하는 실시간 NSSS 열수력 모델 (ARTS)이 통합된 모델을 갖추고 있으며, 해당형식발전소 (WH 3 Loop PWR Plant : 고리 3,4호기, 영광1,2호기 원전)의 여러 가지 과도사고를 실시간으로 정상, 비정상, 비상운전 등으로 모의할 수 있도록 개발되었다. 모의결과 주요 과도 상태의 결과가 해석한 결과와 잘 일치하였으며, 해당형식 발전소 과도 분석이나 규제요원 훈련에 이용될 계획이다.

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