• 제목/요약/키워드: nuclear-power plant

검색결과 3,369건 처리시간 0.03초

원자력 발전소 분산 제어 시스템을 위한 고신뢰 통신망의 설계 (Design of a Reliable Network for DCS in Nuclear Power Plant)

  • 이성우;임한석
    • 대한전기학회:학술대회논문집
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    • 대한전기학회 1997년도 추계학술대회 논문집 학회본부
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    • pp.588-590
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    • 1997
  • In this paper, a highly reliable communication network for DCS in nuclear power plant is designed. The structure and characteristics of DCS in nuclear power plant is briefly explained. The features needed for a communication network for DCS in nuclear power plant is described. According to the abovo features, the layer structure of the communication network is determined and each layer is designed in detail.

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Load Test Simulator Development for Steam Turbine-Generator System of Nuclear Power Plant

  • Jeong, Chang-Ki;Kim, Jong-An;Kim, Byung-Chul;Choi, In-Kyu;Woo, Joo-Hee
    • 제어로봇시스템학회:학술대회논문집
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    • 제어로봇시스템학회 2005년도 ICCAS
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    • pp.1384-1386
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    • 2005
  • This paper focuses on development of load test simulator of a steam turbine-generator in a nuclear power plant. When load is taken off from electrical power network, it is very difficult to effectively control the steam flow to turbine of the nuclear turbine-generator, because of disturbances, such as electrical load and network unbalance on electrical network. Up to the present time, the conventional control system has been used for the load control on nuclear steam generator, owing to the easy control algorithms and the advantage which have been proven on the nuclear power plant. However, since there are problems with stability control during low power and start-up, only a highly experienced operator can operate during those procedures. Also, a great deal of time and an expensive simulator is needed for the training of an operator. The KEPRI is developed simulator for 600MW nuclear power plant to take a test of generator load rejection, throttle valve, and turbine load control. Total load test is implemented before start up.

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영광 원자력 발전소 주변 환경 방사능 측정에 관한 연구 (The study on Measuring of Environmental Radioactivity in the Vicinity of Yonggwang Nuclear Power Plant)

  • 박종섭
    • 자원환경지질
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    • 제32권3호
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    • pp.273-280
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    • 1999
  • In order to protect inhabitans' health and to collect data for prediction of the effcts from accidental emission of rasioactive materials from nuclear power plant, exposed dose rate be monitored within the limit dose rate. This research was carried out to investigate the accumulation of environmental radioactivity around Younggwang Nuclear Power Plant, and to infer and in infer and assay the additional exposed dose rate of inhabitants in Younggwang site from the operation of nuclear plant operation. External radiation dose rate, radiation environmental samples, and exposed dose rate of inhabitants in Younggwang site were investigated for estimaing environment activity in the vicinity of the nuclear power plant area. For the external radiation dose rate, the result showed that range of normal variation was found and any artificial radioisotope was not deteted in the analysis of environmental samples. Exposed dose rate of inhabitants was lower than 0.4% of the limit value of ICRP and it may be concluded that there was no effect on inhabitants and environment from the operation of nuclear power plant.

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SOME POWER UPRATE ISSUES IN NUCLEAR POWER PLANTS

  • Tipping, Philip
    • Nuclear Engineering and Technology
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    • 제40권4호
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    • pp.251-254
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    • 2008
  • Issues and themes concerned with nuclear power plant uprating are examined. Attention is brought to the fact that many candidate nuclear power plants for uprating have anyway been operated below their rated power for a significant part of their operating life. The key issues remain safety and reliability in operation at all times, irrespective of the nuclear power plant's chronological or design age or power rating. The effects of power uprates are discussed in terms of material aspects and expected demands on the systems, structures and components. The impact on operation and maintenance methods is indicated in terms of changes to the ageing surveillance programmes. Attention is brought to the necessity checking or revising operator actions after power up-rating has been implemented.

A Study on Feasibility Evaluation for Prognosis Systems based on an Empirical Model in Nuclear Power Plants

  • Lee, Soo Ill
    • International Journal of Safety
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    • 제11권1호
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    • pp.26-32
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    • 2012
  • This paper introduces a feasibility evaluation method for prognosis systems based on an empirical model in nuclear power plants. By exploiting the dynamical signature characterized by abnormal phenomena, the prognosis technique can be applied to detect the plant abnormal states prior to an unexpected plant trip. Early $operator^{\circ}{\emptyset}s$ awareness can extend available time for operation action; therefore, unexpected plant trip and time-consuming maintenance can be reduced. For the practical application in nuclear power plant, it is important not only to enhance the advantages of prognosis systems, but also to quantify the negative impact in prognosis, e.g., uncertainty. In order to apply these prognosis systems to real nuclear power plants, it is necessary to conduct a feasibility evaluation; the evaluation consists of 4 steps (: the development of an evaluation method, the development of selection criteria for the abnormal state, acquisition and signal processing, and an evaluation experiment). In this paper, we introduce the feasibility evaluation method and propose further study points for applying prognosis systems from KHNP's experiences in testing some prognosis technologies available in the market.

원자력 발전소의 해수전해설비 폐수소를 활용한 PEM 연료전지 발전 시스템에 관한 연구 (A study on the power plant system combined with PEM fuel cell and the wasted hydrogen from the sea water electrolyzer of nuclear power plants)

  • 최종원;이주형;차석원;김민수
    • 한국신재생에너지학회:학술대회논문집
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    • 한국신재생에너지학회 2010년도 춘계학술대회 초록집
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    • pp.124.2-124.2
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    • 2010
  • Generally, a coolant of the nuclear power plant is manufactured by electrolyzing the sea water near the plant for making the sodium hypochlorite(NaOCl), which is used for sterilizing the bacteria and the shellfishes sticking to the drains or the pumps at the outlet of the cooling system due to $8-10^{\circ}C$ warmer temperature than the inlet sea water. During manufacturing the sodium hypochlorite, the hydrogen with the high purity is also produced at the anode side of the electrolyzer. This paper describes a novel power plant system combined with the polymer electrolyte membrane(PEM) fuel cell, the wasted hydrogen from the sea water electrolyzer and the wasted heat of the nuclear power plant. The present status over the exhausted hydrogen at twenty nuclear power plants in Korea was investigated in this study, from which an available power generation is estimated. Furthermore, the economic feasibility of the PEM fuel cell power plant is also evaluated by a current regulations over the power production and exchange using a renewable energy shown in Korea Power Exchange(KRX).

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Development of RCM Framework for Implementation on Safety Systems of Nuclear Power Plant

  • Kim, Tae-Woon;Brijendra Singh;Park, Chang K.;Chang, Tae-Whee;Song, Jin-Bae
    • 한국원자력학회:학술대회논문집
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    • 한국원자력학회 1996년도 춘계학술발표회논문집(2)
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    • pp.631-636
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    • 1996
  • This paper presents a Reliability Centered Maintenance (RCM) framework for implementation on safety system of nuclear power plant (NPP). RCM is a systematic methodology to optimize the surveillance and maintenance tasks for critical components which provides efficiently and effectively reliability of system and safety of plant. Maintenance of the safety systems is essential for its safe and reliable operation. Reliability Centered Maintenance at NPP is the program which assure that plant system remains within original design criteria and that is not adversely affected during the plant life time. Aim of this paper is to provide the RCM framework to implement it on safety systems. RCM framework is described in four major steps.

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Safety assessment of Generation III nuclear power plant buildings subjected to commercial aircraft crash Part II: Structural damage and vibrations

  • Qu, Y.G.;Wu, H.;Xu, Z.Y.;Liu, X.;Dong, Z.F.;Fang, Q.
    • Nuclear Engineering and Technology
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    • 제52권2호
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    • pp.397-416
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    • 2020
  • Investigations of the commercial aircraft impact effect on nuclear island infrastructures have been drawing extensive attention, and this paper aims to perform the safety assessment of Generation III nuclear power plant (NPP) buildings subjected to typical commercial aircrafts crash. At present Part II, based on the verified finite element (FE) models of aircrafts Airbus A320 and A380, as well as the NPP containment and auxiliary buildings in Part I of this paper, the whole collision process is reproduced numerically by adopting the coupled missile-target interaction approach with the finite element code LS-DYNA. The impact induced damage of NPP plant under four impact locations of containment (cylinder, air intake, conical roof and PCS water tank) and two impact locations of auxiliary buildings (exterior wall and roof of spent fuel pool room) are evaluated. Furthermore, by considering the inner structures in the containment and raft foundation of NPP, the structural vibration analyses are conducted under two impact locations (middle height of cylinder, main control room in the auxiliary buildings). It indicates that, within the discussed scenarios, NPP structures can withstand the impact of both two aircrafts, while the functionality of internal equipment on higher floors will be affected to some extent under impact induced vibrations, and A380 aircraft will cause more serious structural damage and vibrations than A320 aircraft. The present work can provide helpful references to assess the safety of the structures and inner equipment of NPP plant under commercial aircraft impact.

원자력발전소와 갑상선암 논란 이후 원자력에 대한 인식 조사 (Perception Survey of Nuclear Power after the Nuclear Plant and Thyroid Cancer Controversy)

  • 이재헌;박은태
    • 한국방사선학회논문지
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    • 제11권1호
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    • pp.19-25
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    • 2017
  • 본 연구는 부산광역시 거주민을 대상으로 원전주변 갑상선암 논란에 따른 원자력에 대한 전반적 인식을 분석하기 위해 위험도, 발전방식에 대한 선호도 및 경제성, 사전-사후 원자력에 대한 인식 등을 조사하였다. 그 결과, 원전 주변 갑상선암 논란을 계기로 국민들의 원자력에 대한 인식에 변화가 있는 것으로 나타났으며, 특히 사건 이전과 비교하여 위험성 요인에서 가장 큰 폭의 상승을 보였다(p<0.05). 이러한 원자력 위험성에 대한 부정적 인식은 집단의 차이에 의해 다르게 표출되는 것으로 분석되었다. 이는 과학적이고 객관적인 근거에 입각하기보다는 개인마다 상이한 선행경험이나 다른 사람과의 상호작용을 통해 획득한 정보에 기인하는 것으로 판단된다. 향후 국민들의 수준을 고려한 원자력 정책을 수립하기 위해서는 국민들의 원자력에 대한 태도와 견해를 이해하려는 노력과 무엇보다도 원자력에 대한 과학적 신뢰가 보장되어야 할 것으로 사료된다.

플랜트 EPC 기업의 해외 원자력 발전 프로젝트 진출방안 (Penetration of Korean EPC Companies into International Market for Nuclear Power Plant)

  • 조찬형;문승재;유호선
    • 플랜트 저널
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    • 제5권3호
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    • pp.66-73
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    • 2009
  • This study aims to develop a strategy for South Korean companies to penetrate into the global NPP(nuclear power plant) market with their strength as the sixth biggest nuclear power generator in the world. With 20 nuclear plants in commercial operation and 6 more in construction, South Korea has the best technology in construction and operation of NPP. Despite these capabilities as demonstrated on its domestic market, Korean companies' constraint to enter and play a key role in global NPP market would be the lack of experience in overseas NPP projects, original technologies, and diplomatic effectiveness. This study analyzes the competitiveness of Korean standardized nuclear power plant, construction management skills, construction technologies, manufacturing equipment and materials and operation skills. In this research the current status of existing NPP and the forecast of building NPP according to countries was analyzed in order to work out strategies with technology, cost-effectiveness, and diplomatic consideration.

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