• 제목/요약/키워드: Nuclear Power Generation System

검색결과 263건 처리시간 0.024초

시스템 다이내믹스(SD)에 의한 국내 전력산업의 효율성 제고에 관한 연구: 원자력산업을 중심으로 (A SD approach to the Efficiency Improvement of Electric Power Industry in Korea: Focused on the Nuclear Industry)

  • 이명호;이희상;장인성;최봉식;허훈
    • 한국경영과학회지
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    • 제26권2호
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    • pp.99-109
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    • 2001
  • In this study, we tried to build a model which can deal with the efficient and effective operation of electric power industry, especially focused on the nuclear industry. Here, SD (System Dynamics) approach is used to visualize the underlying phenomenon of the nuclear power industry. SD is a methodology for studying and managing complex feedback systems, such as one finds in business and other social systems. The spend of SD applications has grown extensively and now encompasses work in corporate planning and policy design, public management and policy, biological and medical modeling, energy and the environment. Recently, according to the report from KEPCO (Korea Electric Power Corporation), they are considering delaying a new power plant construction. It may be based upon business fluctuation downsized from Korean economic crisis in 1997 and freezing of construction funds due to unstable foreign exchange rate. At this point, we need disparately a kind of strategic model that would contribute to cope with the current business situation, energy generation, production, and resulting pollution. Specifically, this model, using SD approach, starts with the detailed drawing of influence diagram, which describes those relevant key points on nuclear power generation systems in electric power industry of Korea. These include such factors as the operation of nuclear industry and parameters related to the decision making for business policy. Based upon the above-mentioned influence diagram drawn, we developed SD simulation model to evaluate and analyze strategic management of KEPCO. Based on our analysis, we could demonstrate how simulation model can be applied to the real electric power generation in Korea.

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발전소 보호계통 주기적 점검 알고리즘에 관한 연구 (A Study on the Periodic Surveillance Algorithm for the Nuclear Power Plant Protection System)

  • 박종범;조황
    • 대한전기학회:학술대회논문집
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    • 대한전기학회 2001년도 합동 추계학술대회 논문집 정보 및 제어부문
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    • pp.201-203
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    • 2001
  • Safety is emphasized in nuclear power plant system for its characteristic. One of the most important systems to guarantee the safety of nuclear power plant is the PPS(Power protection system). The measurement control system includes PPS, which is similar to the human nervous system, is very important factor not only for the safety but also for the operation. Therefore, developing a technology to level up the performance of measurement system and reliability of the plant will bring cost-effective and safe generation of nuclear power. In this study, I researched composition of digitized PPS and algorithm for cyclic inspection.

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주요국의 원자력이용개발 정책동향 분석 (An Analysis on Policy Trends of the Use and Development of Nuclear Power in Nuclear Advanced Countries)

  • 차종희;조흥곤;양맹호
    • 기술혁신학회지
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    • 제6권4호
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    • pp.462-479
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    • 2003
  • The policy trends of use and the development of nuclear power in the United States, France, United Kingdom. Germany, Russia, China, Japan and Korea are briefly investigated. Nuclear power technology has been developed as the national policy in the nuclear-advanced countries. 50 years has passed since the declaration of "Atoms for Peace" by USA President Eisenhour in December 1953. Recently, it appears to revitalize the nuclear power program in world major countries in order to recover the shortage of electric power and to curb the excess emission of carbon dioxide as well as to secure competitiveness in electricity markets. Advanced countries are making new initiatives for the development of the fourth generation nuclear power system. Furthermore, wide-ranged use and development of nuclear power technologies are expected in district heating in commercial sectors, power in the space exploration, and propulsion power of large tankers and spaceships. High temperature gas cooled nuclear power reactor will be applied for mass production of hydrogen energy in the future.

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발전 제어시스템의 융합보안 연구 (A Study on Convergence Security of Power Generation Control System)

  • 이대성
    • 융합보안논문지
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    • 제18권5_1호
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    • pp.93-98
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    • 2018
  • 한국수력원자력, 한국전력공사, 한국남동발전 등의 발전 제어시스템은 전력을 공급하는 국가의 주요 인프라 시설로 악의적인 해킹 공격이 진행될 경우 그 피해는 상상을 초월한다. 실제로 한국수력원자력은 해킹 공격을 당하여 내부정보가 유출되는 등 사회적인 큰 문제를 야기하였다. 본 연구에서는 최근 이슈가 되고 있는 융합보안 연구에 대해 전력회사 중심의 발전 제어시스템을 대상으로 그 환경을 분석하고, 현황을 분석하여 다양한 발전 제어시스템의 안정화를 위한 전략체계 수립과 대응책을 제시하고자 한다. 다양한 물리적 보안시스템(시설), IT 보안시스템, 출입통제시스템 등에서 나오는 데이터 형태를 정규화하고 통합하여 융합인증을 통해 전체 시스템을 통제하고, 융합관제를 통해 위험을 탐지하는 방법을 제안한다.

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공정열 및 수소생산을 위한 초고온가스로 열평형 분석 (Heat balance analysis for process heat and hydrogen generation in VHTR)

  • 박소영;허균영;유연재;이상일
    • 에너지공학
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    • 제25권4호
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    • pp.85-92
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    • 2016
  • 초고온가스로는 열출력 밀도가 낮아 노심용융의 가능성이 낮으며, 냉각재 상실사고 시 수소 발생 등으로 인한 폭발의 위험도 없다. 안전성 측면의 장점과 더불어 냉각재를 초고온으로 만들어 전력생산이외에 산업시설용 공정열로의 응용도 가능하다. 본 논문에서는 초고온가스로를 일차계통으로 하고, 전력 및 공정열 공급이 가능한 이차계통의 개념 설계를 담고 있다. 기존에 NGNP(Next Generation Nuclear Part)에서 제안한 350 MW 열출력 원자로 모델을 기반으로 수소생산 루프와는 별도로 전력생산을 위한 300 MW의 열에너지를 중간열교환기를 통해 이차계통으로 전달하는 참조모델을 개발하고, 이를 열역학적 측면에서 분석하였으며 이차계통 각 지점에서 주요 설계변수에 따른 효율분석과 최적화개념 연구를 수행하였다.

Development of Performance Analysis System (NOPAS) for Turbine Cycle of Nuclear Power Plant

  • Kim, Seong-Kun;Park, Kwang-Hee
    • Nuclear Engineering and Technology
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    • 제33권1호
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    • pp.34-45
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    • 2001
  • We have needs to develop a performance analysis system that can be used in domestic nuclear power plants to determine performance status of turbine cycle. We developed new NOPAS system to aid performance analysis of turbine cycle . Procedures of performance calculation are improved using several adaptations from standard calculation algorithms based on ASME (American Society of Mechanical Engineers) PTC (Performance Test Code). Robustness in the performance analysis is increased by verification & validation scheme for measured input data. The system also provides useful aids for performance analysis such as graphic heat balance of turbine cycle and components, turbine expansion lines, automatic generation of analysis reports.

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Elasticity of substitution of renewable energy for nuclear power: Evidence from the Korean electricity industry

  • Kim, Kwangil
    • Nuclear Engineering and Technology
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    • 제51권6호
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    • pp.1689-1695
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    • 2019
  • This study suggests a simple economic model to analyze electricity grid that consists of different power sources. The substitutability of renewable energy for nuclear power in Korean electricity transmission network is investigated by suggested model. The monthly data from January 2006 to December 2013 reported by Electricity Power Statistics Information System (EPSIS) of Korea Power EXchange (KPX) are used. To estimate the elasticities of substitution among four power sources (i.e. coal, natural gas, nuclear power, and renewable energy), this paper uses the trans-log cost function model on which local concavity restrictions are imposed. The estimated Hicks-Allen and Morishima elasticity of substitution shows that renewable electricity and nuclear power are complementary. The results also evidenced that renewable electricity and fossil fueled thermal power generation are substitutes.

ON-LINE CALCULATION OF 3-D POWER DISTRIBUTION

  • Park, Y. H.;W. K. In;Park, J. R.;Lee, C. C.;G. S. Auh
    • 한국원자력학회:학술대회논문집
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    • 한국원자력학회 1996년도 춘계학술발표회논문집(1)
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    • pp.459-464
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    • 1996
  • The 3-D power distribution synthesis scheme was implemented in Totally Integrated Core Operation Monitoring System (TICOMS), which is under development as the next generation core monitoring system. The on-line 3-D core power distribution obtained from the measured fixed incore detector readings is used to construct the hot pin power as well as the core average axial power distribution. The core average axial power distribution and the hot pin power of TICOMS were compared with those of the current digital on-line core monitoring system, COLSS, which construct the core average axial power distribution and the pseudo hot pin power. The comparison shows that TICOMS results in the slightly more accurate core average axial power distribution and the less conservative hot pin power. Therefore, these results increased the core operating margins. In addition, the on-line 3-D power distribution is expected to be very useful for the core operation in the future.

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Possibilities of reinforcement learning for nuclear power plants: Evidence on current applications and beyond

  • Aicheng Gong;Yangkun Chen;Junjie Zhang;Xiu Li
    • Nuclear Engineering and Technology
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    • 제56권6호
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    • pp.1959-1974
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    • 2024
  • Nuclear energy plays a crucial role in energy supply in the 21st century, and more and more Nuclear Power Plants (NPPs) will be in operation to contribute to the development of human society. However, as a typical complex system engineering, the operation and development of NPPs require efficient and stable control methods to ensure the safety and efficiency of nuclear power generation. Reinforcement learning (RL) aims at learning optimal control policies via maximizing discounted long-term rewards. The reward-oriented learning paradigm has witnessed remarkable success in many complex systems, such as wind power systems, electric power systems, coal fire power plants, robotics, etc. In this work, we try to present a systematic review of the applications of RL on these complex systems, from which we believe NPPs can borrow experience and insights. We then conduct a block-by-block investigation on the application scenarios of specific tasks in NPPs and carried out algorithmic research for different situations such as power startup, collaborative control, and emergency handling. Moreover, we discuss the possibilities of further application of RL methods on NPPs and detail the challenges when applying RL methods on NPPs. We hope this work can boost the realization of intelligent NPPs, and contribute to more and more research on how to better integrate RL algorithms into NPPs.

ASSESSMENT OF POSSIBILITY OF PRIMARY WATER STRESS CORROSION CRACKING OCCURRENCE BASED ON RESIDUAL STRESS ANALYSIS IN PRESSURIZER SAFETY NOZZLE OF NUCLEAR POWER PLANT

  • Lee, Kyoung-Soo;Kim, W.;Lee, Jeong-Geun
    • Nuclear Engineering and Technology
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    • 제44권3호
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    • pp.343-354
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    • 2012
  • Primary water stress corrosion cracking (PWSCC) is a major safety concern in the nuclear power industry worldwide. PWSCC is known to initiate only in the condition in which sufficiently high tensile stress is applied to alloy 600 tube material or alloy 82/182 weld material in pressurized water reactor operating environments. However, it is still uncertain how much tensile stress is re-quired to generate PWSCC or what causes such high tensile stress. This study was performed to pre-dict the magnitude of weld residual stress and operating stress and compare it with previous experi-mental results for PWSCC initiation. For the study, a pressurizer safety nozzle was selected because it is reported to be vulnerable to PWSCC in overseas plants. The assessment was conducted by nu-merical analysis. Before performing stress analysis for plant conditions, a preliminary mock-up ana-lysis was done. The result of the preliminary analysis was validated by residual stress measurement in the mock-up. After verification of the analysis methodology, an analysis under plant conditions was conducted. The analysis results show that the stress level is not high enough to initiate PWSCC. If a plant is properly welded and operated, PWSCC is not likely to occur in the pressurizer safety nozzle.