• Title/Summary/Keyword: Energy plant

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A study of the effectiveness of Online Maintenance for Nuclear Power Plant (원자력발전소 가동중정비 도입 효용성 고찰)

  • Hyun, Jin Woo;Yeom, Dong Un;Lee, Sang Dae
    • Journal of Energy Engineering
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    • v.29 no.1
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    • pp.52-57
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    • 2020
  • OLM(On-Line Maintenance) is PM(Preventive Maintenance) activity of safety related equipment during running of Nuclear Power Plants. Korea Hydro & Nuclear Power-co.(KHNP) and regulator institute already reviewed the adoption of on-line maintenance in 2010 but now because of changing conditions of nuclear industry it has been halted. Even though that, OLM is one of the most effective programs to enhance safety and operability of Nuclear power plant. Therefore this paper introduce the strengths of OLM and explain why we should apply to Nuclear power plant.

Public-Private Cooperation in the Package Deal for Overseas Energy Resources Acquisition (에너지자원획득을 위한 패키지 딜에서의 민관협력방안연구)

  • Park, Dae-Young;Hur, Jin-Huek;Lee, Tae-Gu;Moon, Seung-Jae;Lee, Jae-Heon;Yoo, Ho-Seon
    • Proceedings of the SAREK Conference
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    • 2008.06a
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    • pp.1123-1127
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    • 2008
  • The public-private cooperation in package deal has been studied for the overseas energy resources acquisition. The effectiveness of the package deal has not been successful because the deal has led by the government organizations. It is difficult for the plant EPC companies to join the packaged deal due to the lack of the whole responsibility organization to support the participation of the package deal. The followings are suggested as the ways to strengthen of the public-private cooperation in this study. 1) the relevant public enterprise privatization 2) establishment of the joint model for leading the plant EPC companies to the package deal 3) establishment of the whole responsibility organization for the public-private cooperation.

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Biofouling and Microbial Induced Corrosion -A Case Study

  • Mohammed, R.A.;Helal, A.M.;Sabah, N.
    • Corrosion Science and Technology
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    • v.7 no.1
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    • pp.27-34
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    • 2008
  • In industrial and fluid handling systems, frequently the protective film forming materials suffer from severe corrosion due to microbial effects. As an example, various micro-organisms, including bacteria, exist in seawater normally fed to power and desalination plants. Unless seawater intakes are properly disinfected to control these microbial organisms, biological fouling and microbial induced corrosion (MIC) will be developed. This problem could destroy metallic alloys used for plant construction. Seawater intakes of cogeneration plants are usually disinfected by chlorine gas or sodium hypochlorite solution. The dose of disinfectant is designed according to the level of contamination of the open seawater in the vicinity of the plant intake. Higher temperature levels, lower pH, reduced flow velocity and oxidation potential play an important role in the enhancement of microbial induced corrosion and bio-fouling. This paper describes, in brief, the different types of bacteria, mechanisms of microbiological induced corrosion, susceptibility of different metal alloys to MIC and possible solutions for mitigating this problem in industry. A case study is presented for the power plant steam condenser at Al-Taweelah B-station in Abu Dhabi. The study demonstrates resistance of Titanium tubes to MIC.

A Proposal of Institutional Prerequisites to the Participation of Virtual Power Plant in Electricity Market under the Smart Grid Paradigm (스마트그리드 하에서 가상발전소의 전력시장 참여를 위한 제도적 선결요건에 관한 제언)

  • Chung, Koo-Hyung;Park, Man-Geun;Hur, Don
    • The Transactions of The Korean Institute of Electrical Engineers
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    • v.64 no.3
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    • pp.375-383
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    • 2015
  • The virtual power plant (VPP) is a new technology to achieve flexibility as well as controllability, like traditional centralized power plants, by integrating and operating different types of distributed energy resources (DER) with the information communication technology (ICT). Though small-sized DERs may not be controlled in a centralized manner, these are more likely to be utilized as power plants for centralized dispatch and participate in the energy trade given that these are integrated into a unified generation profile and certain technical properties such as dispatch schedules, ramp rates, voltage control, and reserves are explicitly implemented. Unfortunately, the VPP has been in a conceptual stage thus far and its common definition has not yet been established. Such a lack of obvious guidelines for VPP may lead to a further challenge of coming up with the business model and reinforcing the investment and technical support for VPP. In this context, this paper would aim to identify the definition of VPP as a critical factor in smart grid and, at the same time, discuss the details required for VPP to actively take part in the electricity market under the smart grid paradigm.

Development of a Leading Performance Indicator from Operational Experience and Resilience in a Nuclear Power Plant

  • Nelson, Pamela F.;Martin-Del-Campo, Cecilia;Hallbert, Bruce;Mosleh, Ali
    • Nuclear Engineering and Technology
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    • v.48 no.1
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    • pp.114-128
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    • 2016
  • The development of operational performance indicators is of utmost importance for nuclear power plants, since they measure, track, and trend plant operation. Leading indicators are ideal for reducing the likelihood of consequential events. This paper describes the operational data analysis of the information contained in the Corrective Action Program. The methodology considers human error and organizational factors because of their large contribution to consequential events. The results include a tool developed from the data to be used for the identification, prediction, and reduction of the likelihood of significant consequential events. This tool is based on the resilience curve that was built from the plant's operational data. The stress is described by the number of unresolved condition reports. The strain is represented by the number of preventive maintenance tasks and other periodic work activities (i.e., baseline activities), as well as, closing open corrective actions assigned to different departments to resolve the condition reports (i.e., corrective action workload). Beyond the identified resilience threshold, the stress exceeds the station's ability to operate successfully and there is an increased likelihood that a consequential event will occur. A performance indicator is proposed to reduce the likelihood of consequential events at nuclear power plants.

A Study on the Optimum of Closed ${CO}_{2}$ Gas Turbine Process for Nuclear Energy Power Plant(I) (원자력 발전소에 대한 밀폐 ${CO}_{2}$ 가스터빈 프로세스의 최적화 연구 I)

  • 이찬규;이종원
    • Transactions of the Korean Society of Mechanical Engineers
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    • v.13 no.3
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    • pp.490-499
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    • 1989
  • These days the closed cycle gas turbine attracts considerable attention due to : (1) The possibility of directly coupling the closed cycle gas turbine with a high temperature gas cooled reactor ; (2) the economical use of dry coolers to reduce the thermal charge of the environment ; and (3) the reduction of pollution and energy consumption, by replacing the domestic hearth by a central heating and power station. In this paper, we selected the optimal cycle from the characteristic of thermodynamic cycle for the optimal design of closed CO$_{2}$ gas turbine cycle usuable in nuclear energy power plant. Also the effects of between the parameters and thermal efficiency were investigated by computer simulation. These results and design data will be added to basics in optimal designing closed CO$_{2}$ cycle gas turbine plant.

A Study on the Power Quality of the Grid connected Photovoltaic Power System (계통 연계형 태양광 발전시스템의 전력품질에 관한 연구)

  • Choi, Hyoung-Bum;Kim, Kyung-Chul;Hwang, Young-Rok
    • Journal of the Korean Institute of Illuminating and Electrical Installation Engineers
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    • v.25 no.8
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    • pp.88-98
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    • 2011
  • Development and use of renewable energy due to environmental problems and depletion of energy affect grid-connected power system around the world. Therefore this paper analyzes the characteristic of gird connected photovoltaic power generation system which it is available to connect the utility. Renewable energy photovoltaic power system has been linked to the system to analyze the impact of photovoltaic system. MATLAB / Simulink program is modeled and analyzed on power quality of a photovoltaic power plant. It is measured that power data for the Grid connected photovoltaic power plant with instantaneous measuring, 3sec measuring, 10min measuring for 7 days. Harmonic field measurement have shown that the harmonic contents of a waveform varies with time. A cumulative probability approach is the most commonly used method to solve time varying harmonics. so, it is used 50[%] cumulative probability approach. This paper provides an in depth analysis on power quality field measurement of the Grid connected photovoltaic power plant.

The Plant-specific Impact of Different Pressurization Rates in the Probabilistic Estimation of Containment Failure Modes

  • Ahn, Kwang-ll;Yang, Joon-Eon;Ha, Jae-Joo
    • Nuclear Engineering and Technology
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    • v.35 no.2
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    • pp.154-164
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    • 2003
  • The explicit consideration of different pressurization rates in estimating the probabilities of containment failure modes has a profound effect on the confidence of containment performance evaluation that is so critical for risk assessment of nuclear power plants. Except for the sophisticated NUREG-1150 study, many of the recent containment performance analyses (through Level 2 PSAs or IPE back-end analyses) did not take into account an explicit distinction between slow and fast pressurization in their analyses. A careful investigation of both approaches shows that many of the approaches adopted in the recent containment performance analyses exactly correspond to the NUREG-1150 approach for the prediction of containment failure mode probabilities in the presence of fast pressurization. As a result, it was expected that the existing containment performance analysis results would be subjected to greater or less conservatism in light of the ultimate failure mode of the containment. The main purpose of this paper is to assess potential conservatism of a plant-specific containment performance analysis result in light of containment failure mode probabilities.

Forecasting Methane Gas Concentration of LFG Power Plant Using Deep Learning (딥러닝 기법을 활용한 매립가스 발전소 포집공의 메탄가스 농도 예측)

  • Won, Seung-hyun;Seo, Dae-ho;Park, Dae-won
    • Journal of the Korean Society of Mineral and Energy Resources Engineers
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    • v.55 no.6
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    • pp.649-659
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    • 2018
  • In this study, after operational data for a landfill gas power plant were collected, the methane gas concentration was predicted using a deep learning method. Concentrations of methane gas, carbon dioxide, hydrogen sulfide, oxygen concentration, as well as data related to the valve opening degree, air temperature and humidity were collected from 23 pipeline bases for 88 matches from January to November 2017. After the deep learning model learned the collected data, methane gas concentration was estimated by applying other data. Our study yielded extremely accurate estimation results for all of the 23 pipeline bases.

Neutron dose rate analysis of the new CONSTOR® storage cask for the RBMK-1500 spent nuclear fuel

  • Narkunas, Ernestas;Smaizys, Arturas;Poskas, Povilas;Naumov, Valerij;Ekaterinichev, Dmitrij
    • Nuclear Engineering and Technology
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    • v.53 no.6
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    • pp.1869-1877
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    • 2021
  • This paper presents the neutron dose rate analysis of the new CONSTOR® RBMK-1500/M2 storage cask intended for the spent nuclear fuel storage at Ignalina Nuclear Power Plant in Lithuania. These casks are designed to be stored in a new "closed" type interim storage facility, with the capacity to store up to 202 CONSTOR® RBMK-1500/M2 casks. In 2016 y, the "hot trials" of this new facility were conducted and 10 CONSTOR® RBMK-1500/M2 casks loaded with the spent nuclear fuel were transported to the dedicated storage places in this facility. During "hot trials", the dose rate measurements of the CONSTOR® RBMK-1500/M2 casks were performed as the dose rate is one of the critical parameter to control and it must be below design (and safety) criteria. Therefore, having the actual data of the spent nuclear fuel characteristics, the neutron dose rate modeling of the CONSTOR® RBMK-1500/M2 cask loaded with this particular fuel was also performed. Neutron dose rate modeling was performed using MCNP 5 computer code with very detailed geometrical representation of the cask and the fuel. The obtained modeling results were compared with the measurement results and it was revealed, that modeling results are generally in good agreement with the measurements.