• Title/Summary/Keyword: CEDMCS

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Development of KNGR-CEDMCS Prototype Using DCS for Nuclear Power Plant (원전용 분산제어시스템을 이용한 차세대 원전 제어봉 구동장치제어시스템 원형 개발)

  • Cheon, Jong-Min;Lee, Jong-Moo;Kim, Choon-Kyung;Park, Min-Kook;Kwon, Soon-Man;Shin, Jong-Ryeol
    • Proceedings of the KIEE Conference
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    • 2004.07d
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    • pp.2275-2277
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    • 2004
  • Korea Next Generation Reactor(KNGR) is in the midst of being developed and will exceed Korea Standard Nuclear Power Plant(KSNP) economically. Domestic Instrumentation and Control(I&C) systems shall be applied to KNGR and the development of Control Element Drive Mechanism Control System(CEDMCS) considered as an essential part in nuclear I&C system will be dealt with in this paper. The newly developed CEDMCS has the control cabinet using the nuclear Distributed Control System(DCS) made in Korea and the power cabinet produced by our research institute and interfaced with the DCS control cabinet.

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Design Review of A Power Converter Topology for CEDM Driving (CEDM 구동용 전력변환회로 설계 검토)

  • Lee, J.M.;Kim, C.K.;Cheon, J.M.;Park, M.K.;Kwon, S.M.
    • Proceedings of the KIEE Conference
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    • 2006.07d
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    • pp.1919-1920
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    • 2006
  • This paper deals with the design review of a power converter topologies for CEDMCS (Control Element Drive Mechanism Control System). The CEDMCS provides the control signals and motive power to operate the CEDMS. The CEDM's raise and lower the CEAs (Control Element Assemblies) in the reactor core. The CEAs are constructed with the Boron-10 isotope which has a high microscopic cross section of absorption for thermal neutrons. This characteristic causes the addition of negative reactivity when a CEA is inserted and positive reactivity when it is withdrawn from the reactor core.

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A Design of Main Control Unit in CRCS/CEDMCS (원자로 제어봉구동장치제어시스템 주제어부 설계)

  • Cheon, Jong-Min;Lee, Jong-Moo;Kim, Choon-Kyoung;Kwon, Soon-Man;Shin, Jong-Ryeol
    • Proceedings of the KIEE Conference
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    • 2004.11c
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    • pp.559-561
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    • 2004
  • In this paper, we design two types of Main Control Unit for Control Rod Control System and Control Element Drive Mechanism Control System, respectively, using a domestic Distributed Control System(DCS) developed to localize the instrumentation and control(I&C) system for nuclear power plant(NPP). There are many parts developed by domestic skills and being operated successfully in NPP, but the development of I&C system as an essential part has been slow in progress. We will show the great possibility of developing peculiar Korean I&C system by applying this domestic DCS to nuclear I&C system and confirming its successful operation.

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Operation Test of Control Element Drive Mechanism Using a Power Controller (전력제어기를 이용한 제어봉 구동장치 동작시험)

  • Kim, Choon-Kyung;Lee, Jong-Moo;Jeong, Soon-Hyun;Cheon, Jong-Min;Kweon, Soon-Man
    • Proceedings of the KIEE Conference
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    • 2004.11c
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    • pp.741-743
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    • 2004
  • In this paper, we describe a Control Element Drive Mechanism(CEDM) operation test using a Power Controller. By testing, we can catch the mechanical and electrical characteristics of CEDM and obtain the information about the improvement of CEDM and the design of CEDM power cabinet. The power controller for CEDM introduced in this paper can input firing angles directly into gate drive circuits of thyristors so that this method can be used to derive the maximum and minimum values of firing angles within available limits for a 3-phase half-wave rectifier. Angle inputs help us understand each coil's response characteristics. Since this power controller generates a serial sequence for CEDM insertion and withdrawal operations, we may judge whether CEDM works correctly as expected or not in each phase of a step movement.

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Design of Power Topology for CEDM Driving (CEDM 구동용 Power Topology 설계)

  • Lee, J.M.;Kim, C.K.;Cheon, J.M.;Park, M.K.;Kwon, S.M.
    • Proceedings of the KIEE Conference
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    • 2005.10b
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    • pp.576-578
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    • 2005
  • This paper deals with the design of power topology for nuclear power plants. Although rod control system is still classified into non-safety class. much attention on its reliability issue has been given so far because of its importance for the stable operation of the reactor in the plant. In terms of technical aspects, proposed design is reviewed to satisfy system requirements. This paper deals with a design of power topology for driving Control Element Drive Mechanism (CEDM) that is used to withdraw or insert control rods in nuclear reactor.

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Lesson learned: Target-based independent S/W verification and validation for CEDMCS (교훈: 목표지향 제어봉제어계통 독립 소프트웨어 확인 및 검증)

  • Lee, jayoung;Sohn, kwangyoung;Lee, sangseok;Lee, junku;Park, geunok
    • Annual Conference of KIPS
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    • 2013.05a
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    • pp.932-933
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    • 2013
  • 단순 부품부터 계통까지 기존의 아날로그 제품들이 최근 들어 펌 웨어(Firmware)와 고수준의 컴퓨터 언어로 구현된 응용 소프트웨어를 포함하는 디지털 설비로 바뀌고 있다. 따라서 어느 때 보다 소프트웨어의 확인 및 검증의 중요성이 대두되고 있으며, 이를 위해 학계뿐만 아니라 국제표준 기관에서 확인 및 검증을 위한 지침을 제시하고 있는 실정이다. 본 논문은 원자력발전소 출력을 제어하는 제어봉제어계통의 업그레이드와 관련하여 IEEE 1012 에 따라 수행된 독립 확인 및 검증 업무를 요약하고, 이를 통해 얻은 교훈을 기술한다.

Large-Scale Current Source Development in Nuclear Power Plant (원전에 사용되는 직류전압제어 대전류원의 개발)

  • Jong-ho Kim;Gyu-shik Che
    • Journal of Advanced Navigation Technology
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    • v.28 no.3
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    • pp.348-355
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    • 2024
  • A current source capable of stably supplying current as a measurement medium is required in order to measure and test important facilities that require large-scale measurement current, such as a control element drive mechanism control system(CEDMCS), in case of dismantling a nuclear power plant. However, it can provides only voltage power as a source, not current, although direct voltage controlled constant current source is essential to test major equipment. That kind of source is not available to supply stable constant current regardless of load variation. It is just voltage supplier. Developing current source is not easy other than voltage source. Very large-scale current source up to ampere class more than such ten times of normal current is inevitable to test above mentioned equipment. So, we developed large-scale current source which is controlled by input DC voltage and supplies constant stable current to object equipment according to this requirement. We measured and tested nuclear power plant equipment using given real site data for a long time and afforded long period load test, and then proved its validity and verification. The developed invetion will be used future installed important equipment measuring and testing.