• 제목/요약/키워드: power shutdown

검색결과 300건 처리시간 0.237초

시편의 열화에 따른 가스터빈 로터볼트 기계적 강도평가 (Evaluation for mechanical hardness of gas turbine rotor bolt according to deterioration of specimen)

  • 길두송;안연식;박상기
    • 동력기계공학회지
    • /
    • 제15권4호
    • /
    • pp.19-24
    • /
    • 2011
  • The operational efficiency of domestic gas turbine is about 25% and it is now in the trend of the gradual growth in spite of the severe temperature, frequent starting and shutdown according to the environmental management and the energy-efficient use. Rotor bolts of gas turbine in power plants have been the cause of defects because these gas turbines have been operated for a long time under the high pressure and temperature environment experiencing the aging change and stress concentration of the bonded part. The connection parts of the bolt revealed various failure shape and these parts were elongated under very low pressure when operated in the relaxed condition. The cause is in the lack of the metal distribution in the bottle lack area and the cap screw of the bolt is broken totally in case that the nut is fastened in most cases. Gas turbine rotor bolts are connected to the rotor wheel and these bolts caused the vibration, the bulk accident of the rotor in the event that the coupling power among these bolts was relaxed. Therefore, we would like to evaluate the soundness of the main part of the gas turbine rotor bolt through the measurement of the inner condition change along with the mechanic deterioration and temperature, stress in the gas turbine rotor material.

장대관로를 이용한 소수력 발전량 향상을 위한 설계요소에 관한 연구 (A Study of Design factors for Increasing Energy Production in Small Hydro power with Using Long Pipe)

  • 김현한;김광호
    • 전기학회논문지
    • /
    • 제63권8호
    • /
    • pp.1134-1139
    • /
    • 2014
  • Recently the need for renewable energy development is expanding due to the global climate change, the environmental issues and the limited fossil energy resources. Dependence of energy on overseas is high in Korea. To resolve the environmental problems and to improve the energy independence rate, the development of renewable energy is more required. The small hydro power, one of the renewable energy resources, has been developing and operating from a long time ago. If we are new developing a small hydro power with the use existing dams and reservoirs, we will design the length of inlet pipe and the diameter suitable for it. However, in case of using the existing water supply pipe which had been designed suitable for water service, the designer has to review and check that the pipe is suitable for operating a generator. In this paper, the design of small hydro power using the existing long pipe of water supply, we suggest the optimum way to reduce the water hammer in pipe which causes the unsteady flow during the load-shutdown of generator, the generator operation plan for the stable supply of water and the design factor of determining the generator capacity through the analysis between discharge and head-loss.

확장된 소내전원 상실 사고시의 대체대응활동 완화를 위한 비교 연구: 시스템 엔지니어링 관점으로 (A Comparative Study on Mitigation Alternatives in Response to an Extended SBO for APR1400 Using Systems Engineering)

  • 이슬람 사브리 엘라스와크흐;오승종;임학규
    • 시스템엔지니어링학술지
    • /
    • 제12권2호
    • /
    • pp.91-99
    • /
    • 2016
  • The safety of nuclear power plants has received much attention; this safety largely depends on the continuous availability of electrical energy source during all modes of nuclear power plant operation. A station blackout (SBO) describes the loss of the off-site electric power, the failure of the emergency diesel generators, and the unavailability of the alternate AC (AAC) power. Consequently, all systems that are AC powered such as the safety injection, shutdown cooling, component cooling water, and essential service water systems are unavailable. The aim of this study is to investigate the deficiencies of the existing alternatives for coping with an extended SBO for APR1400 design. The method is analyzing the existing deficiencies and proposing an optimal solution for the NPP design during the extended SBO. This study, established a new passive system, called passive decay heat removal system (PDHRS), using systems engineering approach.

Derivation of preliminary derived concentration guideline level (DCGL) by reuse scenario for Kori Unit 1 using RESRAD-BUILD

  • Park, Sang June;Byon, Jihyang;Ban, Doo Hyun;Lee, Suhee;Sohn, Wook;Ahn, Seokyoung
    • Nuclear Engineering and Technology
    • /
    • 제52권6호
    • /
    • pp.1231-1242
    • /
    • 2020
  • The Kori Unit 1 will be decommissioned after a permanent shutdown in June 2017. South Korea has a 0.1 mSv/yr exposure limit standard for limited or unlimited site release. This is South Korea's first commercial NPP; therefore, if the containment building is reused as a memorial hall, it will contribute to the improvement of public understanding and enhance the public's acceptance of NPPs. Also, existing Kori Unit 1 nuclear power plant manpower resources can be reused after decommissioning and resident staff and memorial hall visitors can activate nearby commercial areas. Therefore, such a reuse scenario may also prevent an economic recession. The exposure dose was calculated using the following scenarios: worker in the containment building, visitor in the containment building, and worker in buildings other than the containment building. The exposure dose in the buildings was calculated by the RESRAD-BUILD developed by the Argonne National Laboratory (ANL). The preliminary exposure dose and derived concentration guideline level (DCGL) were derived.

클라우드 환경에서 다중 클라이언트를 위한 동적 전원관리 시스템 (A Dynamic Power Management System for Multiple Client in Cloud Computing Environment)

  • 차승민;이봉환
    • 한국정보통신학회논문지
    • /
    • 제16권2호
    • /
    • pp.213-221
    • /
    • 2012
  • 본 논문에서는 클라우드 컴퓨팅 환경에서 효율적인 에너지 절감을 위한 동적 전원관리 시스템을 제안한다. 제안한 시스템은 사용자에게 할당된 가상 머신 운용을 위한 키보드와 마우스의 움직임을 감지하고, 가용메모리와 CPU 활용률을 모니터링하게 된다. 만약 시스템이 일정 시간동안 키보드와 마우스의 움직임을 감지하지 못하거나, CPU와 가용 메모리가 미리 정의된 임계값에 도달하게 되면 가상머신 관리자 프로그램은 클라이언트에게 종료 명령을 내리게 되어 상당한 전력절감이 가능하다. 개발된 시스템은 대학 내 실제 컴퓨터 실습실에 적용하여 그 성능을 평가하였다.

선형 근사 평활 발전 비용함수를 이용한 경제급전 문제의 최적화 (Optimization of Economic Load Dispatch Problem Using Linearly Approximated Smooth Fuel Cost Function)

  • 이상운
    • 한국인터넷방송통신학회논문지
    • /
    • 제14권3호
    • /
    • pp.191-198
    • /
    • 2014
  • 본 논문은 복잡한 비평활 발전비용함수를 가진 경제급전의 최적화 문제를 풀기 위해 단순히 선형 근사함수를 이용하는 방법을 제안하였다. 제안된 알고리즘은 비평활 발전비용 함수를 선형으로 근사시키고, 요구량이 현재의 발전량을 초과하는 경우 발전단가가 비싼 발전기의 가동을 중지시키고, 발전단가가 보다 큰 발전기의 발전량을 감소시켜 요구량과 발전량의 균형을 맞추는 개념을 도입하였다. 경제급전 문제의 시험사례로 빈번히 활용되고 있는 데이터에 대해 제안된 알고리즘을 적용한 결과 기존의 휴리스틱 알고리즘의 최적화 해를 획기적으로 감소시킬 수 있었으며, 현재 실무적으로 적용되고 있는 2차 평활함수 근사법과 유사한 결과를 얻었다.

고진등수 영역이 보강된 APR1400 설계지반응답스펙트럼의 개발 (Development of the DGRS enriched in the high frequency range for APR1400)

  • 장영선;김태영;주광호;김종학
    • 한국지진공학회:학술대회논문집
    • /
    • 한국지진공학회 2001년도 추계 학술발표회 논문집 Proceedings of EESK Conference-Fall 2001
    • /
    • pp.67-74
    • /
    • 2001
  • This paper presents the Safe Shutdown Earthquake(SSE) input motion for the seismic design of the Advanced Power Reactor 1400(APR1400). The Design Ground Response Spectra(DGRS) far the SSE is based on the design spectrum specified in regulatory Guide(RG) 1.60 of U.S. Nuclear Regulatory Commission(US NRC), anchored to a Peak Ground Acceleration(PGA) of 0.3g and enriched in the high frequency range. This SSE seismic input motion is to be applied to the seismic analysis as the free-field seismic motion at the ground surface of both the rock and generic soil sites fur APRI1400. The enrichment for APR1400 seismic input motion is performed considering the current US NRC regulations, the seismic hazard studies performed by the Lawrence Livermore National Laboratory (LINL) and Electric Power Research Institute(EPRI) for the Central and Eastern United States nuclear power plant sites, and the seismic input motions used in the design certifications of the three existing U.S. advanced standard plants. It is represented by a set of DGRS and the accompanying Target Power Spectral Density(PSD) Function in both the horizontal and vertical directions.

  • PDF

Application of the Leak Before Break(LBB) Concept to a Heat Exchanger in a Nuclear Power Plant

  • Kwon, Jae-Do;Lee, Choon-Yeol;Lee, Yong-Son;Sul, Il-Chan
    • Journal of Mechanical Science and Technology
    • /
    • 제15권1호
    • /
    • pp.10-20
    • /
    • 2001
  • The leak before break(LBB) concept is difficult to apply to a structure with a thin tube that is immersed in a water environment. A heat exchanger in a nuclear power plant is such a structure. The present paper addresses an application of the LBB concept to a heat exchanger in a nuclear power plant. The minimum leaked coolant amount(approximately 37.9 liters) containing the radioactive material which can activate the radiation detector device installed in near the heat exchanger is assumed. A postulated initial flaw size that can not grow to a critical flaw size within the time period to activate the radiation detector is justified. In this case, the radiation detector can activate the warning signal caused by coolant leakage from initially postulated flaws of the heat exchanger. The nuclear plant can safely shutdown when this occurs. Since the postulated initial flaw size can not grow to the critical flaw size, the structural integrity of the heat exchanger is not impeded. Particularly the informational scenario presented in this paper discusses an actual nuclear plant.

  • PDF

분극저항에 의한 온라인 부식속도 측정 시스템에 관한 연구 (Study on an On-line Measurement System of Corrosion Rate by Linear Polarization Resistance)

  • 문전수;이재근;이재봉;박필양
    • Corrosion Science and Technology
    • /
    • 제11권4호
    • /
    • pp.135-140
    • /
    • 2012
  • The linear polarization resistance method is one of the widely used techniques for the corrosion rate monitoring in the water circulating systems of plants. The measurement is simple and rapid, so that a continuous on-line monitoring is possible without any shutdown of plants. A 2-electrode polarization corrosion rate measurement system was installed in a laboratory using a data acquisition board and PC. The signal processing parameters were optimized for the accurate corrosion rate measurement, and the polarization resistance was compensated with the solution resistance measured by the high frequency sine wave signal of an output channel. The precision of corrosion rate data was greatly improved by removing the initial noise signals on measuring the polarization resistance.

Securing a Cyber Physical System in Nuclear Power Plants Using Least Square Approximation and Computational Geometric Approach

  • Gawand, Hemangi Laxman;Bhattacharjee, A.K.;Roy, Kallol
    • Nuclear Engineering and Technology
    • /
    • 제49권3호
    • /
    • pp.484-494
    • /
    • 2017
  • In industrial plants such as nuclear power plants, system operations are performed by embedded controllers orchestrated by Supervisory Control and Data Acquisition (SCADA) software. A targeted attack (also termed a control aware attack) on the controller/SCADA software can lead a control system to operate in an unsafe mode or sometimes to complete shutdown of the plant. Such malware attacks can result in tremendous cost to the organization for recovery, cleanup, and maintenance activity. SCADA systems in operational mode generate huge log files. These files are useful in analysis of the plant behavior and diagnostics during an ongoing attack. However, they are bulky and difficult for manual inspection. Data mining techniques such as least squares approximation and computational methods can be used in the analysis of logs and to take proactive actions when required. This paper explores methodologies and algorithms so as to develop an effective monitoring scheme against control aware cyber attacks. It also explains soft computation techniques such as the computational geometric method and least squares approximation that can be effective in monitor design. This paper provides insights into diagnostic monitoring of its effectiveness by attack simulations on a four-tank model and using computation techniques to diagnose it. Cyber security of instrumentation and control systems used in nuclear power plants is of paramount importance and hence could be a possible target of such applications.