• 제목/요약/키워드: generator failure

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Analysis of Insulation Diagnosis and Failure in Stator Windings of Air-Cooled Gas Turbine Generator

  • Kim, Hee-Dong;Kong, Tae-Sik;Kim, Kyeong-Yeol
    • KEPCO Journal on Electric Power and Energy
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    • 제2권3호
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    • pp.421-424
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    • 2016
  • In order to evaluate the insulation deterioration in the stator windings of air-cooled gas turbine generators(119.2 MVA, 13.8 kV) which has been operating for more than 15 years, diagnostic test and AC dielectric breakdown test were performed on phases A, B and C. Diagnostic test included measurements of AC current, dissipation factor, partial discharge (PD) magnitude and capacitance. ${\Delta}I$ and ${\Delta}tan{\delta}$ in all three phases (A, B, and C) of generator stator windings showed that they were in good condition but PD magnitude indicated marginally serviceable condition. After the diagnostic test, an AC overvoltage test was performed by gradually increasing the voltage applied to the generator stator windings until electrical insulation failure occurred, in order to determine the breakdown voltage. Although phase A of generator stator windings failed at breakdown voltage of 29.0 kV, phases B and C endured the 29.0 kV. The breakdown voltage in all three phases was higher than that expected for good-quality windings (28.6 kV) in a 13.8 kV class generator.

수력 발전기 제어시스템의 계자상실 모델링과 시뮬레이션 (Modeling and Simulation of Loss of Excitation of Hydro Generator Control System)

  • 박철원
    • 전기학회논문지P
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    • 제63권2호
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    • pp.74-80
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    • 2014
  • Generator protection device has to detects an internal fault conditions in generator and abnormal operating conditions must be due to the hazards. Loss of excitation may cause generator itself failure as well as serious operating problem in power system, and then requires an appropriate response of generator protection device. Details modeling of generator control system and analysis of transient states in generator are important for optimal operation in power plants. In addition, the fault simulation data are also used for testing the characteristics of IED. In this paper, the hydro generator control system using PSCAD/EMTDC, visual simulation for power systems, was modeled. The generator control system which is composed of generator, turbine, exciter, governor was implemented. The parameters of generator control system model were obtained from field power plant. Loss of excitation simulations were performed while varying the fixed load. Several signals analysis were also performed so as to analyze transients phenomena.

두개의 평행한 축방향 관통균열이 존재하는 증기발생기 세관의 최적 파손예측모델 (Optimum Failure Prediction Model of Steam Generator Tube with Two Parallel Axial Through-Wall Cracks)

  • 이진호;송명호;최영환;김낙철;문성인;김영진
    • 대한기계학회:학술대회논문집
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    • 대한기계학회 2003년도 추계학술대회
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    • pp.1186-1191
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    • 2003
  • The 40% of wall criterion, which is generally used for the plugging of steam generator tubes, may be applied only to a single crack. In the previous study, a total of 9 failure models were introduced to estimate the local failure of the ligament between cracks and the optimum coalescence model of multiple collinear cracks was determined among these models. It is, however, known that parallel axial cracks are more frequently detected during an in-service inspection than collinear axial cracks. The objective of this study is to determine the plastic collapse model which can be applied to the steam generator tube containing two parallel axial through-wall cracks. Nine previously proposed local failure models were selected as the candidates. Subsequently interaction effects between two adjacent cracks were evaluated to screen them. Plastic collapse tests for the plate with two parallel through-wall cracks and finite element analyses were performed for the determination of the optimum plastic collapse model. By comparing the test results with the prediction results obtained from the candidate models, a plastic zone contact model was selected as an optimum model.

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Optimum Global Failure Prediction Model of Inconel 600 Thin Plate with Two Parallel Through-Wall Cracks

  • Moon Seong In;Kim Young Jin;Lee Jin Ho;Song Myung Ho;Choi Young Hwan
    • Nuclear Engineering and Technology
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    • 제36권4호
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    • pp.316-326
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    • 2004
  • The $40\%$ of wall criterion, which is generally used for the plugging of steam generator tubes, is applied only to a single crack. In a previous study, a total number of 9 failure models were proposed to estimate the local failure of the ligament between cracks, and the optimum coalescence model of multiple collinear cracks was determined among these models. It is, however known that parallel axial cracks are more frequently detected than collinear axial cracks during an in-service inspection. The objective of this study is to determine the plastic collapse model that can be applied to steam generator tubes containing two parallel axial through-wall cracks. Three previously proposed local failure models were selected as the candidates. Subsequently, the interaction effects between two adjacent cracks were evaluated to screen them. Plastic collapse tests for the plate with two parallel through-wall cracks and finite element analyses were performed to determine the optimum plastic collapse model. By comparing the test results with the prediction results obtained from the candidate models, a COD base model was selected as an optimum model.

발전기 구성요소의 신뢰도 모델 조합을 이용한 고장확률 예측 (Failure Prediction of the Generator Using a Combined Reliability Model of its Individual Components)

  • 이성훈;변융태;김진오
    • 대한전기학회:학술대회논문집
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    • 대한전기학회 2006년도 추계학술대회 논문집 전력기술부문
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    • pp.372-374
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    • 2006
  • This paper presents a methodology to predict a failure probability related to the aging generating units in Korea power system. Each generator is represented by a combined reliability model of its individual components, which is determined by failure data. The Weibull distribution is used to calculate failure probability and its parameters are obtained from Type II Censoring. Consequently, the proposed methods would likely to permit utilities to reduce overall costs in the new deregulated environment.

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2레벨용 부스트 컨버터를 이용한 소형풍력발전기 제동장치 설계에 관한 연구 (A Study on Design of Control Device on Small Wind Generator Using 2-Level Boost Converter)

  • 문채주;장영학;소순열;박태식;정문선;윤영천
    • 전기학회논문지
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    • 제62권10호
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    • pp.1481-1486
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    • 2013
  • The small wind generator with existing mechanical control system has a frequent failure and malfunction, and its maintenance is difficult. In this paper, an electric control method using a boost converter for small wind generator was suggested. The suggested 2-level boost converter control device was manufactured and its experimental operation were conducted on a wind generator with 200 [W] capacity. As a result of experimental device, the control by a boost converter was executed at the point that the output voltage of a wind generator became 36 [V] so it could be identified that the output voltage of a wind generator diminished and then it became 0 [V] after 5 [sec]. Besides, in case of applying the method suggested in this paper to a small wind power generation facility for street lights, it is expected to reduce its maintenance by preventing a frequent failure of a generator and to improve its utilization rate.

Fick's second law 를 이용한 수냉식 발전기 고정자 권선의 건전성 예지 (Health prognostics of stator Windings in Water-Cooled Generator using Fick's second law)

  • 윤병동;장범찬;김희수;배용채
    • 한국소음진동공학회:학술대회논문집
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    • 한국소음진동공학회 2014년도 추계학술대회 논문집
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    • pp.533-538
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    • 2014
  • Power generator is one of the most important component of electricity generation system to convert mechanical energy to electrical energy. I t designed robustly to maintain high system reliability during operation time. But unexpected failure of the power generator could happen and it cause huge amount of economic and social loss. To keep it from unexpected failure, health prognostics should be carried out In this research, We developed a health prognostic method of stator windings in power generator with statistical data analysis and degradation modeling against water absorption. We divided whole 42 windings into two groups, absorption suspected group and normal group. We built a degradation model of absorption suspected winding using Fick's second law to predict upcoming absorption data. Through the analysis of data of normal group, we could figure out the distribution of data of normal windings. After that, we can properly predict absorption data of normal windings. With data prediction of two groups, we derived upcoming Directional Mahalanobis Distance (DMD) of absorption suspected winding and time vs DMD curve. Finally we drew the probability distribution of Remaining Useful Life of absorption suspected windings.

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증기발생기 전열관 다중파단-피동보조급수냉각계통 사고 실험 기반 안전해석코드 SPACE 검증 (Verification of SPACE Code with MSGTR-PAFS Accident Experiment)

  • 남경호;김태우
    • 한국안전학회지
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    • 제35권4호
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    • pp.84-91
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    • 2020
  • The Korean nuclear industry developed the SPACE (Safety and Performance Analysis Code for nuclear power plants) code and this code adpots two-phase flows, two-fluid, three-field models which are comprised of gas, continuous liquid and droplet fields and has a capability to simulate three-dimensional model. According to the revised law by the Nuclear Safety and Security Commission (NSSC) in Korea, the multiple failure accidents that must be considered for accident management plan of nuclear power plant was determined based on the lessons learned from the Fukushima accident. Generally, to improve the reliability of the calculation results of a safety analysis code, verification work for separate and integral effect experiments is required. In this reason, the goal of this work is to verify calculation capability of SPACE code for multiple failure accident. For this purpose, it was selected the experiment which was conducted to simulate a Multiple Steam Generator Tube Rupture(MSGTR) accident with Passive Auxiliary Feedwater System(PAFS) operation by Korea Atomic Energy Research Institute (KAERI) and focused that the comparison between the experiment results and code calculation results to verify the performance of the SPACE code. The MSGR accident has a unique feature of the penetration of the barrier between the Reactor Coolant System (RCS) and the secondary system resulting from multiple failure of steam generator U-tubes. The PAFS is one of the advanced safety features with passive cooling system to replace a conventional active auxiliary feedwater system. This system is passively capable of condensing steam generated in steam generator and feeding the condensed water to the steam generator by gravity. As the results of overall system transient response using SPACE code showed similar trends with the experimental results such as the system pressure, mass flow rate, and collapsed water level in component. In conclusion, it could be concluded that the SPACE code has sufficient capability to simulate a MSGTR accident.

소수력발전기 절연특성분석 (Analysis of Insulation Characteristic for Small Hydro Generator)

  • 오봉근;장정호;이광호;강동식
    • 한국신재생에너지학회:학술대회논문집
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    • 한국신재생에너지학회 2008년도 춘계학술대회 논문집
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    • pp.142-145
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    • 2008
  • Electrical insulation of small hydro generator stator winding is one of the most important parts in generator facilities. Some stator winding insulation problems can be identified through analysis of insulation diagnostic test. So, Diagnosis of stator winding insulation is an important measure of ensuring the safe operation and extending the remaining life of small hydro generator. This paper presents case studies of insulation failure in generator stator windings and the results of insulation diagnostic test for small hydro generator stator windings. Especially, Conducting the insulation diagnostic test before the generator installed in site is very important process to keep the good insulation condition in service.

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원전용 비상디젤발전기 국외 손상사례 분석에 관한 연구 (A Study on the Analysis of Failures Related to Emergency Diesel Generators in Overseas Nuclear Power Plants)

  • 장정환;김진성;정해동;조권회
    • 한국압력기기공학회 논문집
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    • 제5권1호
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    • pp.32-37
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    • 2009
  • The emergency diesel generator (EDG) in a nuclear power plant (NPP) shall start within 10 secondss and supply electrical power to engineered safety features within one minute and less if a loss of offsite power (LOOP), A design-basis event, or their combination occur. Each NPP has an EDG set consisting of two diesel generators for redundancy. In addition to the EDG set, an alternate Alternating Current Diesel Generator (AAC DG) is installed and shared by several units to cope with a station black out (SBO), i.e., loss of the offsite power concurrent with reactor trip and unavailability of the EDG set. The objective of this study is to analyze the failure data of emergency diesel generators reported in overseas nuclear power plants.

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