• 제목/요약/키워드: Reactor Protection System

검색결과 158건 처리시간 0.024초

송전급 초전도한류기의 적용에 따른 선로보호용 비율전류차동계전기의 동작특성 및 보호협조 분석 (Analysis on the Operation Characteristics and Protection Coordination between the Current Ratio Differential Relay for Line Protection and the Trigger-type SFCL in the Power Transmission System)

  • 조용선;김진석;임성훈;김재철
    • 전기학회논문지
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    • 제62권7호
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    • pp.925-930
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    • 2013
  • The fault current of the power transmission system is greater than that of the power distribution system. Therefore, the introduction of superconducting fault current limiter (SFCL) is more needed to reduce the increased fault current. The trigger-type SFCL consists of the high-temperature superconducting element (HTSC), the current limiting reactor (CLR) and the circuit breaker (CB). The trigger-type SFCL can be used to supplement the disadvantages of the resistive-type SFCL. The operation characteristics of the current ratio differential relay which is usually applied to the protection device of the power transmission system are expected to be affected under fault conditions and the applicability of the trigger-type SFCL. In this paper, we analyzed the operating characteristics, by the fault conditions, between the current ratio differential relay for line protection and the trigger-type SFCL in the power transmission system through the PSCAD/EMTDC simulation.

정형기법을 이용한 Safety-Critical System 개발 방법론 (Development Methodology of Safety-Critical System Using Formal Method)

  • 성창훈;이나영;오승록;최진영
    • 한국정보과학회:학술대회논문집
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    • 한국정보과학회 2000년도 가을 학술발표논문집 Vol.27 No.2 (1)
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    • pp.486-488
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    • 2000
  • 본 연구는 정형기법을 사용하여 Safety-Critical System의 개발 방법론을 제시한다. Safety-Critical System의 전체적인 개발 과정을 제시하고 Safety-Critical System 중의 하나인 원자력 발전소 시스템 중 Reactor Protection System(RPS)을 정형 명세(Formal Specification)하고 정형 검증(Formal Verification)하는 과정과 그에 따른 각 과정의 Compliance를 확인하는 예를 든다. 여기서 정형 명세에는 Software Cost Reduction(SCR)이하는 도구가 사용되었고, 정형 검증에는 SPIN이, Compliance를 확인하는 데에는 Prototype Verification System(PVS)를 사용하였다.

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Data Management and Communication Networks for Man-Machine Interface System in Korea Advanced Liquid MEtal Reactor : Its Functionality and Design Requirements

  • Cha, Kyung-Ho;Park, Gun-Ok;Suh, Sang-Moon;Kim, Jang-Yeol;Kwon, Kee-Choon
    • 한국원자력학회:학술대회논문집
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    • 한국원자력학회 1998년도 춘계학술발표회논문집(1)
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    • pp.291-296
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    • 1998
  • The DAta management and Communication NETworks (DACONET), Which it is designed as a subsystem for Man-Machine Interface System of Korea Advanced LIquid MEtal Reactor(KALIMER MMIS) and advanced design concept is approached, is described. The DACONET has its roles of providing the real-time data transmission and communication paths between MMIS systems, providing the quality data for protection, monitoring and control of KALIMER and logging the static and dynamic behavioral data during KALIMER operation. The DACONET is characterised as the distributed real-time system architecture with high performance, Future direction, in which advanced technology is being continually applied to Man-Machine interface System Development of Nuclear Power Plants, will be considered for designing data management and communication networks of KALIMER MMIS

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국내계통 보호시스템을 고려한 22.9kV 초전도케이블/한류기 설계사양 제안 (Specifications of 22.9kV HTS cables and FCLs considering protection systems in Korean power distribution system)

  • 이승렬;박종영;윤재영;이병준;양병모
    • 한국초전도ㆍ저온공학회논문지
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    • 제11권3호
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    • pp.50-54
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    • 2009
  • In Korea, 22.9kV 50MVA HTS (High Temperature Superconducting) cables and 630A/3kA hybrid SFCLs (Superconducting Fault Current Limiters) have been or are being developed by LS Cable, LS Industrial System, and Korea Electric Power Research Institute. They will be installed at Icheon 154kV Substation for real-power-distribution-system operation in 2010. This paper proposes specification of current limiting resistor/reactor for the SFCL and fault current condition of the HTS cable for applying the superconducting devices to Korean power distribution system, from the viewpoint of power system protection.

FAULT TREE ANALYSIS OF KNICS RPS SOFTWARE

  • Park, Gee-Yong;Koh, Kwang-Yong;Jee, Eunk-Young;Seong, Poong-Hyun;Kwon, Kee-Choon;Lee, Dae-Hyung
    • Nuclear Engineering and Technology
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    • 제40권5호
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    • pp.397-408
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    • 2008
  • This paper describes the application of a software fault tree analysis (FTA) as one of the analysis techniques for a software safety analysis (SSA) at the design phase and its analysis results for the safety-critical software of a digital reactor protection system, which is called the KNICS RPS, being developed in the KNICS (Korea Nuclear Instrumentation & Control Systems) project. The software modules in the design description were represented by function blocks (FBs), and the software FTA was performed based on the well-defined fault tree templates for the FBs. The SSA, which is part of the verification and validation (V&V) activities, was activated at each phase of the software lifecycle for the KNICS RPS. At the design phase, the software HAZOP (Hazard and Operability) and the software FTA were employed in the SSA in such a way that the software HAZOP was performed first and then the software FTA was applied. The software FTA was applied to some critical modules selected from the software HAZOP analysis.

A BEHAVIOR-PRESERVING TRANSLATION FROM FBD DESIGN TO C IMPLEMENTATION FOR REACTOR PROTECTION SYSTEM SOFTWARE

  • Yoo, Junbeom;Kim, Eui-Sub;Lee, Jang-Soo
    • Nuclear Engineering and Technology
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    • 제45권4호
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    • pp.489-504
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    • 2013
  • Software safety for nuclear reactor protection systems (RPSs) is the most important requirement for the obtainment of permission for operation and export from government authorities, which is why it should be managed with well-experienced software development processes. The RPS software is typically modeled with function block diagrams (FBDs) in the design phase, and then mechanically translated into C programs in the implementation phase, which is finally compiled into executable machine codes and loaded on RPS hardware - PLC (Programmable Logic Controller). Whereas C Compilers are fully-verified COTS (Commercial Off-The-Shelf) software, translators from FBDs to C programs are provided by PLC vendors. Long-term experience, experiments and simulations have validated their correctness and function safety. This paper proposes a behavior-preserving translation from FBD design to C implementation for RPS software. It includes two sets of translation algorithms and rules as well as a prototype translator. We used an example of RPS software in a Korean nuclear power plant to demonstrate the correctness and effectiveness of the proposed translation.

A RESEARCH ON SEAMLESS PLATFORM CHANGE OF REACTOR PROTECTION SYSTEM FROM PLC TO FPGA

  • Yoo, Junbeom;Lee, Jong-Hoon;Lee, Jang-Soo
    • Nuclear Engineering and Technology
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    • 제45권4호
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    • pp.477-488
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    • 2013
  • The PLC (Programmable Logic Controller) has been widely used to implement real-time controllers in nuclear RPSs (Reactor Protection Systems). Increasing complexity and maintenance cost, however, are now demanding more powerful and cost-effective implementation such as FPGA (Field-Programmable Gate Array). Abandoning all experience and knowledge accumulated over the decades and starting an all-new development approach is too risky for such safety-critical systems. This paper proposes an RPS software development process with a platform change from PLC to FPGA, while retaining all outputs from the established development. This paper transforms FBD designs of the PLC-based software development into a behaviorally-equivalent Verilog program, which is a starting point of a typical FPGA-based hardware development. We expect that the proposed software development process can bridge the gap between two software developing approaches with different platforms, such as PLC and FPGA. This paper also demonstrates its effectiveness using an example of a prototype version of a real-world RPS in Korea.