• Title/Summary/Keyword: Individual power plant

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A Measurement of Team Efficiency of Operators in the Advanced Main Control Room of Nuclear Power Plant (국내 원자력발전소 첨단 주제어실 운전원의 팀 효율성 측정 방법에 관한 연구)

  • Kim, Sa-Kil;Byun, Seong-Nam;Lee, Dhong-Hoon
    • Journal of the Ergonomics Society of Korea
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    • v.27 no.1
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    • pp.21-27
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    • 2008
  • An increased use of teams of actors within complex systems has led to the emergence of various approaches for the assessment of different features associated with team performance. Over the last two decades, the performance of teams in complex systems has received considerable attention from the human factors community, and a number of methods have been developed in order to assess and evaluate team performance. The purpose of this paper is to propose a methodology for measuring team efficiency of operators in the advanced main control room of Korean nuclear power plant. Team efficiency is an index which is estimated of gabs between individual performances and team performance. The index was developed to compare among teams through past all performance measurements.

A Development of PC/Ethernet based Fieldbus Network for Large Realtime Data Communication

  • Gwak, Kwi-Yil;Lee, Sung-Woo
    • 제어로봇시스템학회:학술대회논문집
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    • 2005.06a
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    • pp.362-367
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    • 2005
  • Control network adopted in the national power-plant or manufactory are mostly vendor-dependent products, which have their own special specification, components and individual communication methods. These systems not only raise installation cost, but also bring many difficulties to maintenance and extension. To overcome these problems, this paper introduces a development and application case of a new "PC/Ethernet-based fieldbus" architecture and protocol to be used in mid-level fieldbus. The designed system has a basic idea of "3 Layers fieldbus over Standard-LAN" and implemented on PCs. PC gives user friendly environment. By using an open standard Ethernet in layer 1,2, the system has low cost, wide communication bandwidth and high compatibility. Layer 3 protocol designed for large realtime data communication makes user bypass TCP/IP layer and gives user direct access to the Ethernet. This new protocol eliminates potential collision of Ethernet, and transmits large periodic/non-periodic control data by using long-frame/wide-bandwidth of Ethernet effectively, and offers simple API-Services to the upper layer. Since the system have installed in H-power plant simulator and U-nuclear power plant simulator in Korea, it have been proved to be efficient and stable without any trouble in realtime communication service for full-scope plant simulator that has a lot of control elements.

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The Flame Image Observation for Monitoring Management of Pulverized Coals Firings and its Feasibility Test to Boilers for Thermal Power Plant (미분탄 연소의 감시 관리를 위한 화염영상 감시 및 발전용 보일러 적용시험)

  • Baek, Woon-Bo
    • Journal of the Korean Society for Precision Engineering
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    • v.25 no.1
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    • pp.92-98
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    • 2008
  • The flame image observation and analysis has been investigated for combustion monitoring and management of the pulverized coal firing for thermal power plant, especially for lower nitrogen oxide generation and safer operation. We aimed at obtaining the relationship between burner flame image information and emissions of nitrogen oxide and unburned carbon in furnace utilizing the flame image processing methods, by which we quantitatively determine the conditions of combustion on the individual homers. Its feasibility test was undertaken with Samchonpo thermal power plant #4 unit which has 24 burners, through which the system was observed to be effective for evaluating the combustion conditions and continuous monitoring to prevent future loss of ignition.

Effects of District Energy Supply by Combined Heat and Power Plant on Greenhouse Gas Emission Mitigation (열병합발전을 이용한 집단에너지사업의 온실가스 감축효과)

  • Shin, Kyoung-A;Dong, Jong-In;Kang, Jae-Sung;Im, Yong-Hoon;Kim, Da-Hye
    • Journal of Climate Change Research
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    • v.8 no.3
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    • pp.213-220
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    • 2017
  • The purpose of this study is to analyze effects of Greenhouse Gas (GHG) emission reduction in district energy business mainly based on Combined Heat and Power (CHP) plants. Firstly this paper compares the actual carbon intensity of power production between conventional power plants and district energy plants. To allocate the GHG from CHP plants, two of different methods which were Alternative Generation Method and Power Bonus Method, have been investigated. The carbon intensity of power production in district energy plants ($0.43tonCO_2e/MWh$) was relatively lower than conventional gas-fired power plants ($0.52tonCO_2e/MWh$). Secondly we assessed the cost effectiveness of reduction by district energy sector compared to the other means using TIMES model method. We find that GHG marginal abatement cost of 'expand CHP' scenario (-$134/ton$CO_2$) is even below than renewable energy scenario such as photovoltaic power generation ($87/ton$CO_2$). Finally the GHG emission reduction potential was reviewed on the projected GHG emission emitted when the same amount of energy produced in combination of conventional power plants and individual boilers as substitution of district energy. It showed there were 10.1~41.8% of GHG emission reduction potential in district energy compared to the combination of conventional power plants and individual boilers.

Seismic behavior of simplified electrical cabinet model considering cast-in-place anchor in uncracked and cracked concretes

  • Bub-Gyu Jeon;Sung-Wan Kim;Sung-Jin Chang;Dong-Uk Park;Hong-Pyo Lee
    • Nuclear Engineering and Technology
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    • v.55 no.11
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    • pp.4252-4265
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    • 2023
  • In the case of nuclear power plants near end of their design life, a reassessment of the performance of safetyrelated equipment may be necessary to determine whether to shut down or extend the operation of the power plant. Therefore, it is necessary to evaluate the level of performance decline due to degradation. Electrical cabinets, including MCC and switchgear, are representative safety-related equipment. Several studies have assessed the degradation and seismic performance of nuclear power plant equipment. Most of those researches are limited to individual components due to the size of safety-related equipment and test equipment. However, only a few studies assessed the degradation performance of electrical cabinets. The equipment of various nuclear power plants is anchored to concrete foundations, and crack in concrete foundations is one of the most representative of degradation that could be visually confirmed. However, it is difficult to find a study for analysis through testing the effect of cracks in concrete foundations on the response of electrical cabinet internal equipment fixed by anchors. In this study, using a simple cabinet model considering cast-in-place anchor in uncracked and cracked concretes, a tri-axial shaking table tests were performed and the seismic behavior were observed.

A dual Pressure, Steam Injection Combined cycle Power Plant Performance Analysis (2압, 증기분사 복합발전 사이클에 대한 성능해석)

  • Kim, Su-Yong;Son, Ho-Jae;Park, Mu-Ryong;Yun, Ui-Su
    • 연구논문집
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    • s.27
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    • pp.75-86
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    • 1997
  • Combined cycle power plant is a system where a gas turbine or steam turbine is used to produce shaft power to drive a generator for producing electrical power and the steam from the HRSG is expanded in a steam turbine for additional shaft power. Combined cycle plant is a one from of cogeneration. The temperature of the exhaust gases from a gas turbine ranges from $400^\circC$ to $600^\circC$, and can be used effectively in a heat recovery steam generator to produce steam. Combined cycle can be classed as a "topping(gas turbine)" and a "bottoming(steam turbine)" cycle. The first cycle, to which most of the heat is supplied, is called the topping cycle. The wasted heat it produces is then utilized in a second process which operates at a lower temperature level and is therefore referred to as a "bottoming cycle". The combination of gas/steam turbine power plant managed to be accepted widely because, first, each individual system has already proven themselves in power plants with a single cycle, therefore, the development costs are low. Secondly, the air as a working medium is relatively non-problematic and inexpensive and can be used in gas turbines at an elevated temperature level over $1000^\circC$. The steam process uses water, which is likewise inexpensive and widely available, but better suited for the medium and low temperature ranges. It, therefore, is quite reasonable to use the steam process for the bottoming cycle. Only recently gas turbines attained inlet temperature that make it possible to design a highly efficient combined cycle. In the present study, performance analysis of a dual pressure combined-cycle power plant is carried out to investigate the influence of topping cycle to combined cycle performance.

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INSTORE : A PC-Based Database Program for Occupational Radiation Exposure of a Nuclear Power Plant

  • Cho, Yeong-Ho;Kang, Chang-Sun;Mun, Ju-Hyung;Kim, Hak-Su
    • Nuclear Engineering and Technology
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    • v.30 no.4
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    • pp.308-317
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    • 1998
  • Ensuring occupational radiation exposure(ORE) as low as is reasonably achievable(ALARA) has been one of very important requirements in a nuclear power plant. It is well known that about 70 percent of occupational dose has incurred from maintenance jobs in the outage period. To reduce occupational dose effectively, the high-dose jobs in the outage period should be identified with their dose reduction potentials and methods. In this study, a PC-based ORE database program, INSTORE, is developed to evaluate ORE doses in individual jobs, and the ORE data of Kori Units 3 and 4 are assembled to the database. Based on customary job classification, radiation work is classified into 26 main jobs which comprise 61 detailed jobs, and occupational doses are assessed according to each detailed job. As a result, high-dose jobs are identified with dose reduction priority in terms of collective ORE dose. It is recommended that adeqaute dose reduction methods for these jobs should be prepared to improve their working conditions and procedures.

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Virtual Power Plant System using OpenADR2.0 and TASE.2 for Integrated Management of Distributed Energy Resource (분산자원 통합 관리를 위한 OpenADR2.0 및 TASE.2 기반 가상발전소 시스템)

  • Seo, Jong Kwan;Lee, Tae Il;Lee, Whee Sung;Park, Jeom Bae
    • Journal of IKEEE
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    • v.24 no.1
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    • pp.311-318
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    • 2020
  • A virtual power plant is a kind of software power plant that enables participation in power operation by integrally managing individual distributed resources. This paper proposes a common information communication architecture based on the TASE.2 standard and the OpenADR2.0 standard to operate a virtual power plant as a single power system. ESS is designed TASE.2 SBO devices that related objects are mapped to OpenADR2.0 services and composed as a single sequence type. Through simulation verification, it conforms data exchange and operation based on both standards.

Radiation Exposure from Nuclear Power Plants in Korea: 2011-2015

  • Lim, Young Khi
    • Journal of Radiation Protection and Research
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    • v.42 no.4
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    • pp.222-228
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    • 2017
  • Background: On June 18, 2017, Korea's first commercial nuclear reactor, the Kori Nuclear Power Plant No. 1, was permanently suspended, and the capacity of nuclear power generation facilities will be adjusted according to the governments denuclearization policy. In these circumstances, it is necessary to assess the quality of radiation safety management in nuclear power plants in Korea by evaluating the radiation dose associated with them. Materials and Methods: The average annual radiation dose per unit, the annual radiation dose per person, and the annual dose distribution were analyzed using the radiation dose database of nuclear reactors for the last 5 years. The results of our analysis were compared to the specifications of the Nuclear Safety Act and Medical Law in Korea. Results and Discussion: The annual average per unit radiation dose of global major nuclear power generation was 720 man-mSv, while that of Korea's nuclear power plants was 374 manmSv. No workers exceeded 50 mSv per year or 100 mSv in 5 years. The individual radiation dose according to occupational exposure was 0.59 mSv for nuclear workers, 1.77 mSv for non-destructive workers, and 0.8 mSv for diagnostic radiologists. Conclusion: The radiation safety management of nuclear power plants in Korea has achieved the best outcomes worldwide, which is considered to be the result of the as-low-as-reasonably-achievable (ALARA) approach and strict radiation safety management. Moreover, the occupational exposures were also very low.

Analysis of Air Distribution in the Windbox System of the Utility Boiler (보일러 Windbox내 공기공급 계통의 유량분포 해석)

  • Park, Ho-Young;Kim, Sung-Chul
    • Korean Journal of Air-Conditioning and Refrigeration Engineering
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    • v.20 no.9
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    • pp.581-589
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    • 2008
  • The pulverized coal combustion behavior in the utility boiler is very complex since so many physical and chemical processes happen in it, simultaneously. The mixing of pulverized coal with combustion air plays an important role in achieving the efficient combustion and stable boiler operation. The distribution of combustion air supplied to the furnace through the windbox damper system has not been clearly known since the individual measurements of air flow for each air nozzle were not possible, yet. The present study describes the CFD modelling of windbox damper system and aims to obtain the air flow rates and pressure loss coefficients across the present five damper systems, respectively. The one dimensional flow network model has been also established to get air flow distributions across the windbox damper, and applied to the actual plant operation condition. Compared with the designed air flow distribution, the modelled one gives a reasonable agreement. For the actual plant operation, the predicted air flow distribution at each air nozzle is differed with the designed data and strongly affected by the individual opening angle.