• Title/Summary/Keyword: Steam Power plant

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Oil leak detection on a plant by using CCTV camera (CCTV 카메라를 이용한 플랜트 오일 누설 감시)

  • Son, Ki-Sung;Jeon, Seop-Hyeong;Choi, Young-Chul;Park, Jong-Won
    • Proceedings of the Korean Society for Noise and Vibration Engineering Conference
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    • 2011.04a
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    • pp.136-141
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    • 2011
  • In a power plant, an oil and steam leakage is generated once in a while. This is because the operating temperature and pressure of oil are very high. It is very difficult to monitor oil leakage, because oil leakage is almost invisible. Therefore a method to oil leakage detecting quickly and accurately is needs. In this paper, we proposed the method for the detecting oil leakage by using image processing and CCTV. To test the performance of this technique, experiments have been performed for simple case. Results show that the proposed technique is quite powerful in the oil leak detection.

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Development on Integrated Pyrolysis Cogeneration System for Waste Tire Recycling Treatment (폐타이어 재활용 처리를 위한 열분해 열병합 복합공정기술개발)

  • Kim, Seong-Yeon;Ha, Man-Yeong
    • Proceedings of the KSME Conference
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    • 2008.11b
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    • pp.1990-1995
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    • 2008
  • The thermochemical recycling of waste tires by pyrolysis is studied to recover the value added three by-products; a pyrolytic carbon black, a pyrolytic oil, and a non-condensable gas. The exhausted energy from pyrolysis of waste tires is converted for electricity power and process steam in cogeneration system. The characteristics of the pyrolysis recovered by-products as alternative energy resource are investigated with the design of a demonstration and a commercialization plant including cogeneration system, as called integrated pyrolysis cogeneration system.

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Development of Turbine Rotor Bending Straightening Numerical Model using the High Frequency Heating Equipment (고주파 가열 장비를 활용한 터빈로터 휨 교정수식모델 개발)

  • Park, Junsu;Hyun, Jungseob;Park, Hyunku;Park, Kwangha
    • KEPCO Journal on Electric Power and Energy
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    • v.7 no.2
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    • pp.269-275
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    • 2021
  • The turbine rotor, one of the main facilities in a power plant, it generates electricity while rotating at 3600 RPM. Because it rotates at high speed, it requires careful management because high vibration occurs even if it is deformed by only 0.1mm. However, bending occurs due to various causes during turbine operating. If turbine rotor bending occurs, the power plant must be stopped and repaired. In the past, straightening was carried out using a heating torch and furnace in the field. In case of straightening in this way, it is impossible to proceed systematically, so damage to the turbine rotor may occur and take long period for maintenance. Long maintenance period causes excessive cost, so it is necessary to straighten the rotor by minimizing damage to the rotor in a short period of time. To solve this problem, we developed a turbine rotor straightening equipment using high-frequency induction heating equipment. A straightening was validated for 500MW HIP rotor, and the optimal parameters for straightening were selected. In addition, based on the experimental results, finite element analysis was performed to build a database. Using the database, a straightening amount prediction model available for rotor straightening was developed. Using the developed straightening equipment and straightening prediction model, it is possible to straightening the rotor with minimized damage to the rotor in a short period of time.

Welding process for manufacturing of Nuclear power main components (원자력 발전 주기기 제작에 적용되는 용접공정)

  • Jung, In-Chul;Kim, Yong-Jae;Shim, Deog-Nam
    • Proceedings of the KWS Conference
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    • 2010.05a
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    • pp.43-46
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    • 2010
  • As the nuclear power plant has been constructed continuously for several decades in Korea, the welding technology for components manufacturing and installation has been improved largely. Standardization for weld test and qualification was also established systematically according to the concerned code. The welding for the main components requires the high reliability to keep the constant quality level, which means the repeatability of weld quality. Therefore the weld process qualified by thorough test and evaluation is able to be applied for manufacturing. Narrow gap SAW and GTAW process are usually applied for girth seam welding of pressure vessel like Reactor vessel, steam generator, and etc. For the surface cladding with stainless steel and Inconel material, strip welding process is mainly used. Inside cladding of nozzles is additionally applied with Hot wire GTAW and semi-auto welding process. Especially the weld joint having elliptical weld line on curved surface needs a specialized weld system which is automatically rotating with adjusting position of the head torch. The small sized pipe, tube, and internal parts of reactor vessel requests precise weld processes like an automatic GTAW and electron beam welding. Welding of dissimilar materials including Inconel690 material has high possibility of weld defects like a lack of fusion, various types of crack. To avoid these kinds of problem, optimum weld parameters and sequence should be set up through the many tests. As the life extension of nuclear power plant is general trend, weld technologies having higher reliability is required gradually. More development of specialized welding systems, weld part analysis and evaluation, and life prediction for main components should be taken into a consideration extensively.

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Basic Design and Dynamic Simulation of Large Scale Solar Thermal Power Plant (대규모 태양열발전 기본설계 및 동특성 계산)

  • Kim, Jong-Kyu;Kang, Yong-Heack;Kim, Jin-Soo;Yoon, Hwan-Ki;Yu, Chang-Kyun;Lee, Sang-Nam
    • Journal of the Korean Solar Energy Society
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    • v.27 no.1
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    • pp.55-61
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    • 2007
  • This paper describes the procedure and calculation results of basic design and transient variation of performance of 1 MWe large scale solar thermal power plant (STPP) by using the commercial software of THERMOFLEX and TRNSYS, respectively. In order to simulate the transient variation of STPP, the results of basic design are necessary. The design standard of the STPP is 1 MWe generation with solar only at high DNI condition and then 0.6 MWe output power for 1 hour using stored energy when the DNI becomes lower unable to operate normally. The results of basic design show the important design data of flow rates, water/steam conditions at each equipments and the estimated efficiency of STPP. In addition, dynamic simulation results of STPP are predicted and plotted for one year and three different days weather data of Daejeon.

Structural Integrity Assessment of High-Strength Anchor Bolt in Nuclear Power Plant based on Fracture Mechanics Concept (원자력발전소 고강도 앵커 볼트의 파괴역학적 건전성평가)

  • Lim, Eun-Mo;Huh, Nam-Su;Shim, Hee-Jin;Oh, Chang-Kyun;Kim, Hyun-Su
    • Transactions of the Korean Society of Mechanical Engineers A
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    • v.37 no.7
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    • pp.875-881
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    • 2013
  • The failure of a bolted joint owing to stress corrosion cracking (SCC) has been considered one of the most important structural integrity issues in a nuclear power plant. In this study, the failure possibility of bolting, which is used to support the steam generator of a pressurized water reactor, owing to SCC and brittle fracture was evaluated in accordance with guidelines proposed by the Electric Power Research Institute, which are called the Reference Flaw Factor method. For this evaluation, first, detailed finite element stress analyses were conducted to obtain the actual nominal stresses of bolting in which either service loads or bolt preloads were considered. Based on these nominal stresses, the structural integrity of bolting was addressed from the viewpoints of SCC and toughness. In addition, the accuracy of the EPRI Reference Flaw Factor for assessing bolting failure was investigated using finite element fracture mechanics analyses.

A Study on Design of TMR Control System for Steam Turbine (터빈 감시제어용 삼중화 제어시스템 설계에 관한 연구)

  • Ahn, Jong-Bo;Kim, Kook-Hun;Kim, Seog-Joo;Kim, Chun-Kyong;Kim, Jong-Moon
    • Proceedings of the KIEE Conference
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    • 2000.11d
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    • pp.663-665
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    • 2000
  • For the control system of thermal turbine in fuel and nuclear power plant, as high reliability and availability are required, redundant control system is generally applied. This paper presents the configuration and design of such a redundant control system that can be suitable for control and monitoring of the turbine. System components such as I/O system, communication networks, voting system are designed, and especially the new intelligent voter using serial communication are proposed. The characteristics of the implemented control system is independence of the control, protection and monitoring functions, and discrimination of the redundancies, and high availability. The control functions such as speed control, load control, valve control and protective functions such as overspeed and PLU are designed in detail.

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Fault Diagnosis Method based on Feature Residual Values for Industrial Rotor Machines

  • Kim, Donghwan;Kim, Younhwan;Jung, Joon-Ha;Sohn, Seokman
    • KEPCO Journal on Electric Power and Energy
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    • v.4 no.2
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    • pp.89-99
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    • 2018
  • Downtime and malfunction of industrial rotor machines represents a crucial cost burden and productivity loss. Fault diagnosis of this equipment has recently been carried out to detect their fault(s) and cause(s) by using fault classification methods. However, these methods are of limited use in detecting rotor faults because of their hypersensitivity to unexpected and different equipment conditions individually. These limitations tend to affect the accuracy of fault classification since fault-related features calculated from vibration signal are moved to other regions or changed. To improve the limited diagnosis accuracy of existing methods, we propose a new approach for fault diagnosis of rotor machines based on the model generated by supervised learning. Our work is based on feature residual values from vibration signals as fault indices. Our diagnostic model is a robust and flexible process that, once learned from historical data only one time, allows it to apply to different target systems without optimization of algorithms. The performance of the proposed method was evaluated by comparing its results with conventional methods for fault diagnosis of rotor machines. The experimental results show that the proposed method can be used to achieve better fault diagnosis, even when applied to systems with different normal-state signals, scales, and structures, without tuning or the use of a complementary algorithm. The effectiveness of the method was assessed by simulation using various rotor machine models.

Application of Continuous Indentation Technique for Reliability Evaluation in Power Plant Facilities (발전설비 주요배관 신뢰도 확보를 위한 연속압입시험 적용)

  • Park, Sang-Ki;Ahn, Yeon-Shik;Jung, Gye-Jo;Cho, Yong-Sang;Choi, Yeol
    • Journal of the Korean Society for Nondestructive Testing
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    • v.24 no.2
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    • pp.158-162
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    • 2004
  • Reliability of welded structures in power plant facilities is very important, and their reliability evaluation requires exact materials properties. But, the conventional PQR (Procedure Qualification Record) can hardly reflect the real material properties in the field because the test is only done on specimens with simulated welding. Therefore, a continuous indentation technique is proposed in this study for simple and non-destructive testing of in-field structures. This test measures the indentation load-depth curve during indentation and analyzes the mechanical properties such as the yield strength, tensile strength and work hardening index. This technique has been applied to evaluate the tensile properties of the weldment in the main steam pipe and hot reheater pipe in power plants under construction and in operation.

PutStudy of Power Generation and Condensation Efficiency on MSTG of MSW Incineration Plant (폐기물소각설비 중 MSTG설비의 발전 및 응축효율에 관한 연구)

  • Jeon, Kuemha;Jeon, Kwangsik;Ha, Choongrai
    • 한국신재생에너지학회:학술대회논문집
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    • 2010.06a
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    • pp.208.1-208.1
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    • 2010
  • 일일 50톤 처리용량의 도시고형폐기물소각설비의 폐열 보일러에서 생산되는 4.0~6.5 bar의 저압증기를 이용하여 전력을 생산하는 축류식 MSTG설비에 있어서 공급증기압력, 입출구의 압력차이에 의한 발전효율을 비교하고, 저압의 증기의 균질화를 위한 기술분리, 정압유지설비 및 증기터빈의 본체의 기수분리된 증기의 응축효율을 증기공급율, 발전효율별로 비교분석하였다. 공급되는 증기의 압력, 증기터빈의 입출구 압력 차이가 높아짐에 따라, 증기의 응축효율이 증가를 하였으며, 배출되는 증기량에 따른 발전효율의 증가는 없었다. 따라서, 가변적으로 변하는 저압의 증기를 기수분리 및 정압을 유지하여도 증기질의 변동이 없으며 그에 따른 증기의 엔탈피 변화가 없으므로 발전 효율의 향상을 기대하기는 어려웠다.

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