• 제목/요약/키워드: Large Power Plant

검색결과 681건 처리시간 0.028초

국내외 수전해 기술 및 대규모 실증 프로젝트 진행 현황 (Current Status of Water Electrolysis Technology and Large-scale Demonstration Projects in Korea and Overseas)

  • 백종민;김수현
    • 한국수소및신에너지학회논문집
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    • 제35권1호
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    • pp.14-26
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    • 2024
  • Global efforts continue with the goal of transition to a "carbon neutral (net zero)" society with zero carbon emissions by 2050. For this purpose, the technology of water electrolysis is being developed, which can store electricity generated from renewable energies in large quantities and over a long period of time as hydrogen. Recently, various research and large-scale projects on 'green hydrogen', which has no carbon emissions, are being conducted. In this paper, a comparison of water electrolysis technologies was carried out and, based on data provided by the International Energy Agency (IEA), large-scale water electrolysis demonstration projects were analyzed by classifying them by technology, power supply, country and end user. It is expected that through the analysis of large-scale water electrolysis demonstration projects, research directions and road maps can be provided for the development/implementation of commercial projects in the future.

원자력발전소(原子力發電所) 가동중(稼動中) 검사(檢査)의 시험분석(試驗分析)을 위한 자동화연구(自動化硏究) (I) (A Study of Automation for Examination Analysis of Inservice Inspection for Nuclear Power Plant (I))

  • 김욱
    • 비파괴검사학회지
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    • 제5권1호
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    • pp.34-47
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    • 1985
  • The developing country, KOREA where does not possess the natural resources for traditional energy such as oil and gas, so. The nuclear energy is the most single reliable source available for closing the energy gap. For these reason, It is inavoidable to construct the nuclear power plant and to develop technology related nuclear energy. The rate of operation in large nuclear power facilities depends upon the performance of work system through design and construction, and also the applied technology. Especially, it is the most important element that safety and reliability in operation of nuclear power plant. In view of this aspects, Nuclear power plant is performed severe examinations during preservice and inservice inspection. This study provide an automation of analysis for volumetric examination which is required to nuclear power plant components. It is composed as follows: I. Introduction II. Inservice Inspection of Nuclear Power Plant ${\ast}$ General Requirement. ${\ast}$ Principle and Methods of Ultrasonic Test. ${\ast}$ Study of Flaw Evaluation and Design of Classifying Formula for Flaws. III. Design of Automation for Flaw Evaluation. IV. An Example V. Conclusion In this theory, It is classifying the flaws, the formula of classifying flaws and the design of automation that is the main important point. As motioned the above, Owing to such as automatic design, more time could be allocated to practical test than that of evaluation of defects, Protecting against subjective bias tester by himself and miscalculation by dint of various process of computation. For the more, adopting this method would be used to more retaining for many test data and comparative evaluating during successive inspection intervals. Inspite of limitation for testing method and required application to test components, it provide useful application to flow evaluation for volumetric examination. Owing to the characteristics of nuclear power plant that is highly skill intensive industry and has huze system, the more notice should be concentrated as follows. Establishing rational operation plan, developing various technology, and making the newly designed system for undeveloped sector.

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Importance of pumped storage hydroelectric power plant in Turkey

  • Aras, Egemen
    • Advances in Energy Research
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    • 제5권3호
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    • pp.239-254
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    • 2017
  • The world began to search for new energy sources with increasing energy demand. Renewable energy sources are as hydropower important for alternative energy. Countries with high hydroelectric potentials continue to work to utilize hydroelectric power plants in the most efficient way. Pumped storage hydropower plants are an important investment to meet the growing energy needs at peak times and to store energy. Although it produces energy in many countries, pumped storage hydropower plants have not begun to be built in Turkey which has high hydroelectric potential. A new era will be opened for energy production in Turkey where a large number of pumped storage hydropower plants projects are in study phase with the construction of pumped storage hydropower plants and first nuclear power plant.

사용후핵연료저장조의 확률론적안전성평가 수행을 위한 시스템엔지니어링 프로세스 적용 연구 (Systems Engineering Process Approach to the Probabilistic Safety Assessment for a Spent Fuel Pool of a Nuclear Power Plant)

  • 최진태;차우창
    • 시스템엔지니어링학술지
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    • 제17권2호
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    • pp.82-90
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    • 2021
  • The spent fuel pool (SFP) of a nuclear power plant functions to store the spent fuel. The spent fuel pool is designed to properly remove the decay heat generated from the spent fuel. If the cooling function is lost and proper operator action is not taken, the spent fuel in the storage pool can be damaged. Probabilistic safety assessment (PSA) is a safety evaluation method that can evaluate the risk of a large and complex system. So far, the probabilistic safety assessment of nuclear power plants has been mainly performed on the reactor. This study defined the requirements and the functional architecture for the probabilistic safety assessment of the spent fuel pool (SFP-PSA) by applying the systems engineering process. And, a systematic and efficient methodology was defined according to the architecture.

Development of a Fully-Coupled, All States, All Hazards Level 2 PSA at Leibstadt Nuclear Power Plant

  • Zvoncek, Pavol;Nusbaumer, Olivier;Torri, Alfred
    • Nuclear Engineering and Technology
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    • 제49권2호
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    • pp.426-433
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    • 2017
  • This paper describes the development process, the innovative techniques used and insights gained from the latest integrated, full scope, multistate Level 2 PSA analysis conducted at the Leibstadt Nuclear Power Plant (KKL), Switzerland. KKL is a modern single-unit General Electric Boiling Water Reactor (BWR/6) with Mark III Containment, and a power output of $3600MW_{th}/1200MW_e$, the highest among the five operating reactors in Switzerland. A Level 2 Probabilistic Safety Assessment (PSA) analyses accident phenomena in nuclear power plants, identifies ways in which radioactive releases from plants can occur and estimates release pathways, magnitude and frequency. This paper attempts to give an overview of the advanced modeling techniques that have been developed and implemented for the recent KKL Level 2 PSA update, with the aim of systematizing the analysis and modeling processes, as well as complying with the relatively prescriptive Swiss requirements for PSA. The analysis provides significant insights into the absolute and relative importances of risk contributors and accident prevention and mitigation measures. Thanks to several newly developed techniques and an integrated approach, the KKL Level 2 PSA report exhibits a high degree of reviewability and maintainability, and transparently highlights the most important risk contributors to Large Early Release Frequency (LERF) with respect to initiating events, components, operator actions or seismic component failure probabilities (fragilities).

IEC61400-25 국제표준기반 풍력 SCADA시스템을 위한 데이터베이스 설계방안 (A Database Design Method for Wind Power Plant SCADA System based on IEC61400-25)

  • 채창훈;최효열;최준석
    • 정보처리학회논문지:컴퓨터 및 통신 시스템
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    • 제1권3호
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    • pp.151-160
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    • 2012
  • 본 논문에서는 IEC61400-25 국제표준기반 풍력 SCADA 시스템을 위한 데이터베이스 설계를 수행하였다. 국제표준의 도입과 풍력발전의 대형화, 단지화로 인하여 발생하는 방대한 양의 데이터를 처리하기 위하여 체계적 관리는 필수적이다. 복잡하고 다양한 기능의 풍력 데이터들의 특성을 파악하고 사용자의 사전 요구사항을 반영하여 데이터베이스를 설계함으로써 데이터 공간 낭비를 줄이고, 관리의 효율성을 향상시킬 수 있다. 결과적으로 구축, 유지비용과 노력을 줄일 수 있을 것으로 기대한다.

부하변동이 심한 화력발전소의 예상 발전 제어 (Anticipatory Generation Control of Fossil Power Plant for Large and Rapid Recurring Load Fluctuations)

  • 박영문;박종근;김재철;김봉희
    • 대한전기학회논문지
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    • 제35권6호
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    • pp.237-245
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    • 1986
  • 대부분 화력 발전소는 기저부하(base load)운전용으로 설계되어 있어 극심한 부하 변동이 계속되는 부하에 대하여는 일반적으로 적합하지 못하다. 특히 전기로와 압연기가 설치된 제철소에 전력을 공급하는 발전소의 경우 연속적인 심한 부하변동으로 일반적으로 발전소 제어 시스템으로는 적당치 않다. 이 논문에서는 이와 같이 연속적으로 급변하는 부하에 대응할 수 있는 화력 발전소 예상 제어 앨고리즘을 제시 하였다. 상헤한 제어 앨고리즘과 모델 계통에 대한 사례 연구를 첨부하였다.

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마찰진자시스템의 강성중심 변화에 따른 면진된 원전 구조물의 지진응답평가 (Seismic Response Evaluation of Seismically Isolated Nuclear Power Plant with Stiffness Center Change of Friction Pendulum Systems)

  • 석철근;송종걸
    • 한국지진공학회논문집
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    • 제21권6호
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    • pp.265-275
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    • 2017
  • In order to improve the seismic performance of structures, friction pendulum system (FPS) is the most commonly used seismic isolation device in addition to lead rubber bearing (LRB) in high seismicity area. In a nuclear power plant (NPP) with a large self weight, it is necessary to install a large number of seismic isolation devices, and the position of the center of rigidity varies depending on the arrangement of the seismic isolation devices. Due to the increase in the eccentricity, which is the difference between the center of gravity of the nuclear structure and the center of stiffness of the seismic isolators, an excessive seismic response may occur which could not be considered at the design stage. Three different types of eccentricity models (CASE 1, CASE 2, and CASE 3) were used for seismic response evaluation of seismically isolated NPP due to the increase of eccentricity (0%, 5%, 10%, 15%). The analytical model of the seismic isolation system was compared using the equivalent linear model and the bilinear model. From the results of the seismic response of the seismically isolated NPP with increasing eccentricity, it can be observed that the effect of eccentricity on the seismic response for the equivalent linear model is larger than that for the bilinear model.

An Application of Realistic Evaluation Model to the Large Break LOCA Analysis of Ulchin 3&4

  • C. H. Ban;B. D. Chung;Lee, K. M.;J. H. Jeong;S. T. Hwang
    • 한국원자력학회:학술대회논문집
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    • 한국원자력학회 1996년도 춘계학술발표회논문집(2)
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    • pp.429-434
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    • 1996
  • K-REM[1], which is under development as a realistic evaluation model of large break LOCA, is applied to the analysis of cold leg guillotine break of Ulchin 3&4. Fuel parameters on which statistical analysis of their effects on the peak cladding temperature (PCT) are made and system parameters on which the concept of limiting value approach (LVA) are applied, are determined from the single parameter sensitivity study. 3 parameters of fuel gap conductance, fuel thermal conductivity and power peaking factor are selected as fuel related ones and 4 parameters of axial power shape, reactor power, decay heat and the gas pressure of safety injection tank (SIT) are selected as plant system related ones. Response surface of PCT is generated from the plant calculation results and on which Monte Carlo sampling is made to get plant application uncertainty which is statistically combined with code uncertainty to produce the 95th percentile PCT. From the break spectrum analysis, blowdown PCT of 1350.23 K and reflood PCT of 1195.56 K are obtained for break discharge coefficients of 0.8 and 0.5, respectively.

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고압 대전류용 전력변환 점호장치 및 감시시스템 개발 (Development of firing equipment and monitoring system for electric power conversion system for high voltage and large current)

  • 이주현;임익헌;류호선
    • 전력전자학회:학술대회논문집
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    • 전력전자학회 2006년도 전력전자학술대회 논문집
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    • pp.481-484
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    • 2006
  • A electric power conversion system in a pumped storage power plant is important equipment for converting electric motor kinetic energy into electric power. A electric power conversion monitoring system consists of high voltage thyristor firing equipment, fault detection module, data gathering module, real time data processing equipment and man machine interface system. This paper describes electric power conversion system overview, the developed SFC monitoring system configuration including system characteristics, and successful application result to San-Cheong pumped storage power plant.

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