• Title/Summary/Keyword: power plants

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Battery Sizing of Lithium-Based Battery for Emergency Power Supply in Nuclear Power Plants (전 비상전원 적용을 위한 리튬계열전지 용량 설계)

  • Park, Seongyun;Kim, Gunwoo;Lee, Pyeongyeon;Kim, Jonghoon;Park, Sungbeak;Kim, Youngmi
    • The Transactions of the Korean Institute of Power Electronics
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    • v.24 no.5
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    • pp.342-348
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    • 2019
  • The emergency power supplies (EPSs) are required to increase battery sizing for protecting power source loss above designed criteria. This study proposes a sizing method for lithium-based batteries for EPSs in nuclear power plants on the basis of the calculation method for the required energy under variable conditions. The variable conditions are related with the characteristics of lithium-based batteries, such as the temperature of the location of EPS installation, aging, and design margin. The usage of lithium-based battery reduces the cost and installation space and enables the safe and long-term supply of power compared with the use of lead-acid battery.

Severe Accident Analysis for Wolsung Nuclear Power Plants

  • Kwon, Jong-Jooh;Kim, Myung-Ki;Park, Byoung-Chul;Kim, Inn-Seock;Hong, Sung-Yull
    • Proceedings of the Korean Nuclear Society Conference
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    • 1997.05a
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    • pp.464-470
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    • 1997
  • Severe accident analysis has been performed for the Wolsung nuclear power plants in Korea to investigate severe accident phenomena of CANDU-600 reactors as a part of Level II PSA study. The accident sequence analyzed in this paper is loss of active heat sinks(LOAH) which is caused by loss of off-site power, diesel generators, and DC power. ISAAC (Integrated Severe Accident Analysis Code)computer code developed by KAERI (Korea Atomic Energy Research Institute) was used in this analysis. This paper describes the important thermal-hydraulics and source term behaviors in the primary system and inside containment, and the failure mechanism of calandria vessel and containment. In addition, some insights for accident management program(AMP) are also given.

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Analysis of a Communication Network for Control Systems in Nuclear Power Plants and a Case Study (원자력 발전소 제어 계통을 위한 통신망의 해석과 사례 연구)

  • Lee, S.W.;Yoon, M.H.;Moon, H.J.;Shin, C.H.;Lee, B.Y.
    • Proceedings of the KIEE Conference
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    • 1999.07b
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    • pp.1013-1016
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    • 1999
  • In this paper, a real-time communication method using a PICNET-NP(Plant Instrumentation and Control Network for Nuclear Power plant) is proposed with an analysis of the control network requirements of DCS (Distributed Control System) in nuclear power plants. The method satisfies deadline in case of worst data traffics by considering aperiodic and periodic real-time data and others. In addition, the method was used to analyze the data characteristics of the DCS in existing nuclear power plant. The result shows that use of this method meets the response time requirement(100ms)

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Determining the Warming Effect Induced by Photovoltaic Power Plants in neighboring Region Using an Analytical Model (해석학적 모델을 이용한 태양광 발전소 주변 지역의 기온 상승 추정 연구)

  • Kim, Hae-Dong;Huh, Kyong-Chun;Kim, Ji-Hye
    • Journal of Environmental Science International
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    • v.27 no.3
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    • pp.227-231
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    • 2018
  • We studied the warming effect induced by Photovoltaic(PV) power plants in rural areas during summer daytime using a simple analytical urban meteorological model. This analysis was based on observed meteorological elements and the capacity of the PV power plant was 10 MWp. The major axis length of the PV power plant was assumed to be 1km. Data of the necessary meteorological elements were obtained from a special meteorological observation campaign established for a over a PV power plant. We assumed that the wind flowed along the major axis of the PV power plant(1 km). As a result, the air temperature on the downwind side of the PV power plant was estimated to invrease by about $0.47^{\circ}C$.

Selection of Optimal Location and Size of Distributed Generation Considering Power Loss (전력손실을 고려한 분산전원의 최적 위치 및 용량 선정)

  • Lee, Soo-Hyoung;Park, Jung-Wook
    • The Transactions of The Korean Institute of Electrical Engineers
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    • v.57 no.4
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    • pp.551-559
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    • 2008
  • Increase in power consumption can cause a serious stability problem of an electric power system without construction of new power plants or transmission lines. Also, it can generate large power loss of the system. In costly and environmentally effective manner to avoid constructing the new infrastructures such as power plants and transmission lines, etc, the distributed generation(DG) has paid great attentions so far as a solution for the above problem. Selection of optimal location and size of the DG is the necessary process to maintain the stability and reliability of existing system effectively. However, the systematic and cardinal rule for this issue is still open question. In this paper, the method to determine optimal location of the DG is proposed by considering power loss when the DG is connected to an electric power grid. Also, optimal size of not only the corresponding single DG but also the multi-DGs is determined with the proposed systematic approach. The IEEE benchmark 30-bus test system is analyzed to evaluate the feasibility and effectiveness of the proposed method.

Analysis on Wind Turbine Degradation of the Shinan Wind Power Plant (신안풍력발전소 풍력터빈의 성능저하 분석)

  • Kim, Hyun-Goo
    • Journal of the Korean Solar Energy Society
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    • v.33 no.4
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    • pp.46-50
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    • 2013
  • This paper investigated wind turbine degradation quantitatively by analyzing the short-term operation records of the Shinan Wind Power Plant. Instead of a capacity factor which is needed to be normalized its variability due to monthly wind speed change, this study suggests an analysis method by taking the difference between the theoretical power output calculated from the nacelle wind speed and actual power output as the quantitative index of performance degradation. For three-year SCADA data analysis of the Shinan Wind Power Plant, it was confirmed that power output degradation rate of 0.54% per year. This value is within the average reduction rate 0.4%/year~0.9%/year of normalized capacity factor of the onshore wind power plants in U.K. and Denmark; however, lower than the rate 2%/year of Canadian wind power plants.

A Study on Validation Methodology of Fire Retardant Performance for Cables in Nuclear Power Plants (원자력발전소 케이블 난연성능 검증 방법론 개선을 위한 연구)

  • Lee, Sang Kyu;Moon, Young Seob;Yoo, Seong Yeon
    • Journal of the Korean Society of Safety
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    • v.32 no.1
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    • pp.140-144
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    • 2017
  • Fire protection for nuclear power plants should be designed according to the concept of "Defense in Depth" to achieve the reactor safety shutdown. This concept focuses on fire prevention, fire suppression and safe shutdown. Fire prevention is the first line of "Defense in Depth" and the licensee should establish administrative measures to minimize the potential for fire to occur. Administrative measures should include procedures to control handling and use of combustibles. Electrical cables is the major contributor of fire loads in nuclear power plants, therefore electrical cables should be fire retardant. Electrical cables installed in nuclear power plants should pass the flame test in IEEE-383 standard in accordance with NUREG-0800, "Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants". To assure the fire retardant of electrical cables during design life, both aged and unaged cable specimens should be tested in accordance with IEEE-383. It can be generally thought that the flammability of electrical cables has been increased by wearing as time passed, however the results from fire retardant tests performed in U.S.A and Korea indicate the inconsistent tendency of aging and consequential decrease in flammability. In this study, it is expected that the effective methodology for validation of fire retardant performance would be identified through the review of the results from fire retardant tests.

Current Management Status of Mercury Emissions from Coal Combustion Facilities: International Regulations, Sampling Methods, and Control Technologies

  • Lee, Sung-Jun;Pudasainee, Deepak;Seo, Yong-Chil
    • Journal of Korean Society for Atmospheric Environment
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    • v.24 no.E1
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    • pp.1-11
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    • 2008
  • Mercury (Hg), which is mainly emitted from coal-fired power plants, remains one of the most toxic compounds to both humans and ecosystems. Hg pollution is not a local or regional issue, but a global issue. Hg compounds emitted from anthropogenic sources such as coal-fired power plants, incinerators, and boilers, can be transported over long distances. Since the last decade, many European countries, Canada, and especially the United States, have focused on technology to control Hg emissions. Korea has also recently showed an interest in managing Hg pollution from various combustion sources. Previous studies indicate that coal-fired power plants are one of the major sources of Hg in Korea. However, lack of Hg emission data and feasible emission controls have been major obstacles in Hg study. In order to achieve effective Hg control, understanding the characteristics of current Hg sampling methods and control technologies is essential. There is no one proven technology that fits all Hg emission sources, because Hg emission and control efficiency depend on fuel type, configuration of air pollution control devices, flue gas composition, among others. Therefore, a broad knowledge of Hg sampling and control technologies is necessary to select the most suitable method for each Hg-emitting source. In this paper, various Hg sampling methods, including wet chemistry, dry sorbents trap, field, and laboratory demonstrated control technologies, and international regulations, are introduced, with a focus on coal-fired power plants.

RHODIUM SELF-POWERED NEUTRON DETECTOR'S LIFETIME FOR KOREAN STANDARD NUCLEAR POWER PLANTS

  • YOO CHOON SUNG;KIM BYOUNG CHUL;PARK JONG-HO;FERO ARNOLD H.;ANDERSON S. L.
    • Nuclear Engineering and Technology
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    • v.37 no.6
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    • pp.605-610
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    • 2005
  • A method to estimate the relative sensitivity of a self-powered rhodium detector for an upcoming cycle is developed by combining the rhodium depletion data from a nuclear design with the site measurement data. This method can be used both by nuclear power plant designers and by site staffs of Korean standard nuclear power plants for determining which rhodium detectors should be replaced during overhauls.