• Title/Summary/Keyword: Electric Power Plant

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Development of Supply Capability Calculation and Prediction Technology for Generator (발전기 공급능력 산정 및 예측 기술개발)

  • Kim, Euihwan;An, Youngmo;Hong, Eunkee
    • KEPCO Journal on Electric Power and Energy
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    • v.2 no.3
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    • pp.425-431
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    • 2016
  • Supply Capability of the generator, if the maximum demand occurs, refers to the maximum power that can be stably supplied and it is possible to maintain stable power supply to be greater than actual load. However, unexpected power demand and reduction in supply Capability due to stop of unexpected generator in operation can temporarily make a big chaos in power system. In fact, due to a lack of power supply Capability in the country, enforced emergency load adjustment to the September 15, 2011, the circulation power outage has occurred in several cities. As the result, interrupted operation of the elevator and stopped hospital medical equipment led to a great deal of trouble to people's lives, causing a social problem. At that time, it was found that a failed frequency control because of smaller actual supply Capability than that of predicted. The difference was about 1,170 MW with Gas turbine power plant. By accurately calculating the generator supply capability, we can not only grasp the power reserve rate, but also correspond to the time of power supply instability.

Reactor Power Cutback System Test Experience at YGN 4

  • Chi, Sung-Goo;Kim, Se-Chang;Seo, Jong-Tae;Eom, Young-Meen;Wook, Jeong-Dae;Park, Young-Boo
    • Proceedings of the Korean Nuclear Society Conference
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    • 1995.10a
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    • pp.235-241
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    • 1995
  • YGN 3 and 4 are the nuclear power plants having System 80 characteristics with a rated thermal output of 2815 MWth and a nominal net electrical output of 1040 MWe. YGN 3 achieved commercial operation on March 31, 1995 and YGN 4 completed Power Ascension Test (PAT) at 20%, 50%, 80% and 100% power by September 23, 1995. YGN 3 and 4 design incorporates the Reactor Power Cutback System (RPCS) which reduces plant trips caused by Loss of Load (LOL)/Turbine Trip and Loss of One Main Feedwater Pump (LOMFWP). The key design objective of the RPCS is to improve overall plant availability and performance, while minimizing challenges to the plant safety systems. The RPCS is designed to rapidly reduce reactor power by dropping preselected Control Element Assemblies (CEAs) while other NSSS control systems maintain process parameters within acceptable ranges. Extensive RPCS related tests performed during the initial startup of YGN 4 demonstrated that the RPCS can maintain the reactor on-line without opening primary or secondary safety valves and without actuating the Engineered Safety Features Actuation System (ESFAS). It is expected that use of the RPCS at YGN will increase the overall availability of the units and reduce the number of challenges to plant safety systems.

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The analysis of KEPCO $\pm40MVA$ SSSC dynamic characteristics (FACTS Pilot Plant $\pm40MVA$ SSSC 동특성 분석)

  • Yoon Jong Su;Jeon Young Soo;Kim Soo Yeol
    • Proceedings of the KIEE Conference
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    • summer
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    • pp.174-176
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    • 2004
  • FACTS 기술은 송전계통에 전압원 인버터를 설치하여 모선 전압과 전력조류를 제어하므로 송전용량 증대 및 계통 안정도 향상을 가능케하는 신기술이다. 국내에서는 2003년 최초의 FACTS Pilot Plant인 80MVA UPFC가 154kV 강진 변전소에 설치되었다. UPFC는 STATCOM과 SSSC가 DC 커패시터를 통하여 결합된 구조로 되어 모선전압과 유효/무효전력 조류의 독립적인 제어가 가능하며 계통 운전 상황에 따라 STATCOM과 SSSC의 단독운전 또한 가능하다. 따라서 STATCOM 및 SSSC 단독운전시의 계통영향에 대한 분석이 필요하다 본 논문은 EMTDC 모델을 이용하여 현재 운전중인 강진 변전소 UPFC의 직렬 운전모드인 40MVA SSSC의 제어특성과 운전효과 분석에 대하여 기술하였다.

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A study on the speed regulation improvement and water starting time of pumped storaged power plant (양수발전소 속도조정율 향상 및 수력적 부도시간에 관한 연구)

  • Choi, I.K.;Woo, J.H.
    • Proceedings of the KIEE Conference
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    • 1999.07b
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    • pp.743-745
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    • 1999
  • In these days, pumped storaged power plants are under operations mainly for load regulation in power system. After we investigated the governor related electrical circuit of a pumped storaged power plant, we measured speed regulation and dead time of both the governor and the hydraulic system according to the change of variables of the governor during generation. After that the measured speed regulation improved much.

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A Study on the Distribution of Heavy Metal Concentrations in Marine Surface Sediments around Samcheonpo Power Plant (삼천포화력발전소 주변해역 표층퇴적물중의 중금속원소함량 분포 연구)

  • Lee, Doo-Ho;Lim, Ju-Hwan;Jeon, Byeong-Yeol;Jeong, Nyeon-Ho
    • Journal of Environmental Impact Assessment
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    • v.9 no.1
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    • pp.1-11
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    • 2000
  • An environmental geochemical survey of heavy metal distribution in marine surface sediments around the ocean of Samcheonpo coal-fired power plant was conducted to investigate the possibility of coal-ash leakage from ash pond and the associated heavy metal pollution in sedimental deposits due to the operation of the coal-fired power plant. The X-Ray Diffractometry (XRD) analysis showed that the main leakage point of coal-ash was limited to a single site of the first ash pond. It also appeared that the amounts of organic carbon and metal elements were positively correlated to the grain size distribution, and that Co, Cr, Cu, Fe, Ni, and Zn were bounded to organic ligands. However, the distributions of Cd, Hg, and Mn did not have any significant correlation with the sediment grain size and organic matters. In particular, the distribution of Cd appeared to be affected by the concentration of the carbonate materials in the study area.

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Procedure Development and Qualification of the Phased Array Ultrasonic Testing for the Nuclear Power Plant Piping Weld (원자력발전소 배관 용접부 위상배열 초음파검사 절차서 개발 및 기량검증)

  • Yoon, Byung-Sik;Yang, Seung-Han;Kim, Yong-Sik;Lee, Hee-Jong
    • Journal of the Korean Society for Nondestructive Testing
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    • v.30 no.4
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    • pp.317-323
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    • 2010
  • The manual ultrasonic examination for the nuclear power plant piping welds has been demonstrated by using KPD(Korean Performance Demonstration) generic procedure. For automated ultrasonic examination, there is no generic procedure and it should be qualified by using applicable automated equipment. Until now, most of qualified procedures used pulse-echo technique and there is no qualified procedure using phased array technique. In this study, data acquisition and analysis software were developed and phased-array transducer and wedge were designed to implement phased array technique for nuclear power plant in-service inspection. The developed procedure are qualified for performance demonstration for the flaw detection, length sizing and depth sizing. The qualified procedure will be applied for the field examination in the nuclear power plant piping weld inspection.