• 제목/요약/키워드: Transients phenomena

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PSCAD를 이용한 전력용 변압기 모델링과 과도 해석 (Power Transformer Modeling and Transient Analysis using PSCAD)

  • 박철원
    • 전기학회논문지P
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    • 제65권2호
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    • pp.122-129
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    • 2016
  • Current differential protection relaying with second harmonic restraint is the main protection for large capacity power transformer. PSCAD simulation program is widely used for modeling of dynamic varying transients phenomena. This paper deals with a power transformer model and transients analysis using PSCAD software to develop IED for power transformer. Simulation was carried out using a three phase 40MVA, 154/22.9kV, 60Hz, two-winding transformer with Y-Y connection used in actual fields. The paper analyzed transformer magnetizing inrush, external fault, and internal fault conditions with this model in the time domain. In addition, we performed an analysis in the frequency domain using FFT during several conditions.

배전시스템에서의 파라미터에 따른 과도현상 분석 (Transients Analysis for Parameters on Electrical Distribution System)

  • 김재철;오정환;임성정
    • 한국조명전기설비학회지:조명전기설비
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    • 제11권3호
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    • pp.88-96
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    • 1997
  • 본 논문은 배전시스템에서의 파라미터에 따른 과도현상을 분석하였다. 재투입에 의한 순간전압강하와 개폐서지를 분석하였으며, 이를 위해서 22.9[kV] 배전시스템의 실 데이터를 이용하여 다중접지된 모델 시스템을 구성하였다. EMTP 시뮬레이션을 통하여 주상변압기 2차측 수용가에서의 재투입 영향을 분석하였으며, 사고선로와 인근선로에서의 과도현상을 나타냈었다. 또한 사고위치, 부하크기, 부하역률, 캐패시터뱅크의 크기, 재투입 위상각에 대한 파라미터 분석을 하였고, 이들 요소와 재투입에 의한 과도 현상과의 관계를 나타내었다.

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RELAP5 Simulation of the Small Inlet Header Break Test B8604 Conducted in the RD-14 Test Facility

  • Lee, Sukho;Kim, Manwoong
    • Nuclear Engineering and Technology
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    • 제32권1호
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    • pp.57-66
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    • 2000
  • The RELAP5 code has been developed for best-estimate simulation of transients and accidents for pressurized water reactors and their associated systems, but it has not been fully assessed for those of CANDU reactors. However, a previous study suggested that the RELAP5 code could be applicable to simulate the transients and accidents for CANDU reactors. Nevertheless, it is indicated that there are some works to be resolved, such as modeling of headers and multi-channel simulation for the reactor core, etc. Therefore, this study has been initiated with an aim to identify the code applicability for all the postulated transients and accidents in CANDU reactors. In the present study, the small inlet header break experiment (B8604) in the RD-14 test facility was simulated with RELAP5/MOD3.2 code. The RELAP5 results were also compared with both experimental data and those of CATHENA analyses performed by AECL and the analyses demonstrated the code's capability to predict major . phenomena occurring in the transient with sufficient accuracy for both Qualitative and quantitative viewpoint However, some discrepancies in the depressurization of the primary heat transport system after the break and the consequent time delay of the major phenomena were also observed.

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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.

Study of Transients at BOAO

  • Im, Myungshin
    • 천문학회보
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    • 제41권1호
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    • pp.61.1-61.1
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    • 2016
  • As a new way to explore the universe, astronomers are now performing time-domain astronomy by surveying the universe looking for new transient phenomena and taking movies of the universe with telescopes. Large-area, time-series survey of astronomical objects are uncovering many interesting, fast-changing objects that have now been poorly understood before, such as GRBs, tidal disruption phenomena, and new types of supernova. In order to characterize these new, exciting events, it is very critical to perform follow-up observations, and 1-2m telescopes can effectively contribute to such efforts. Since 2007, our group has been performing follow-up observations of gamma-ray bursts (GRBs) and interesting transients using BOAO and other KASI facilities. Here, we present results from several key transient studies that were done by using BOAO: (1) tidal disruption event Swift J1644+57; (2) SN 2011fe that occurred in M101; and (3) several GRB events. These study demonstrates the usefulness of BOAO as a powerful transient follow-up facility. Finally, we will discuss how BOAO research activities can possibly be bolstered in this newly emerging field of astronomy.

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OVERVIEW OF RECENT EFFORTS THROUGH ROSA/LSTF EXPERIMENTS

  • Nakamura, Hideo;Watanabe, Tadashi;Takeda, Takeshi;Maruyama, Yu;Suzuki, Mitsuhiro
    • Nuclear Engineering and Technology
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    • 제41권6호
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    • pp.753-764
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    • 2009
  • JAEA started the LSTF experiments in 1985 for the fourth stage of the ROSA Program (ROSA-IV) for the LWR thermal-hydraulic safety research to identify and investigate the thermal-hydraulic phenomena and to confirm the effectiveness of ECCS during small-break LOCAs and operational transients. The LSTF experiments are underway for the ROSA-V Program and the OECD/NEA ROSA Project that intends to resolve issues in thermal-hydraulic analyses relevant to LWR safety. Six types of the LSTF experiments have been done for both the system integral and separate-effect experiments among international members from 14 countries. Results of four experiments for the ROSA Project are briefly presented with analysis by a best-estimate (BE) code and a computational fluid dynamics (CFD) code to illustrate the capability of the LSTF and codes to simulate the thermal-hydraulic phenomena that may appear during SBLOCAs and transients. The thermal-hydraulic phenomena dealt with are coolant mixing and temperature stratification, water hammer up to high system pressure, natural circulation under high core power condition, and non-condensable gas effect during asymmetric SG depressurization as an AM action.

Wind Pressure Transients in the Tunnel inside a Station Caused by a Passing High Speed Train

  • Nahmkeon Hur;Kim, Sa-Ryang;Kim, Wook;Lee, Sangyeul
    • Journal of Mechanical Science and Technology
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    • 제18권9호
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    • pp.1614-1622
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    • 2004
  • When a High Speed Train (HST) passes through a station with no stop, effects of wind pressure transients caused by this passing train have to be considered for the safety of passengers on the platform and for the possible structural safety problems as well. In Gwangmyeong and Daejeon stations of the Korean high speed railroad, tunnels inside stations for the passing train are proposed to reduce the noise and wind pressure transients to the passengers on the platform. In the present study, transient 3-D full Navier-Stokes solutions with moving mesh to implement train movement are obtained and compared with the results obtained by the towing tank experiment. Investigations on flow phenomena for various train speeds and design modifications are also performed.

Improved prediction of Pump Turbine Dynamic Behavior using a Thoma number dependent Hill Chart and Site Measurements

  • Manderla, Maximilian;Kiniger, Karl N.;Koutnik, Jiri
    • International Journal of Fluid Machinery and Systems
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    • 제8권2호
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    • pp.63-72
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    • 2015
  • Water hammer phenomena are important issues for the design and the operation of hydro power plants. Especially, if several reversible pump-turbines are coupled hydraulically there may be strong unit interactions. The precise prediction of all relevant transients is challenging. Regarding a recent pump-storage project, dynamic measurements motivate an improved turbine modeling approach making use of a Thoma number dependency. The proposed method is validated for several transient scenarios and turns out to improve correlation between measurement and simulation results significantly. Starting from simple scenarios, this allows better prediction of more complex transients. By applying a fully automated simulation procedure broad operating ranges of the highly nonlinear system can be covered providing a consistent insight into the plant dynamics. This finally allows the optimization of the closing strategy and hence the overall power plant performance.

전기설비 사고의 열적 특성 분석 (Analysis of Heat Characteristics for Fault Power Utility)

  • 김기화
    • 한국화재소방학회논문지
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    • 제11권4호
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    • pp.25-31
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    • 1997
  • In this study, EMTP(Electromagnetic Transients Program) which is one of the most well-known computer simulation methods is used to collect the data for a power plant fault. EMTP is the program for an interpretation of the phenomena of electric transients, and is designed to manifest the data of the electric current and voltage etc. at the time of a power plant fault. By EMTP, I analyze the properties of the heat energy which are transferred from the electrics when a power plant fault brings out. In terms of the results of this study, it is able to measure the heat energy at a power plant fault (power transformer) and to be acquired of the related data. And moreover, these data are expected to be used as a standard for the protection of the fire owing to a high voltage power transformer fault.

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Development of a Preliminary PIRT (Phenomena Identification and Ranking Table) of Thermal-Hydraulic Phenomena for SMART

  • Chung, Bub-Dong;Lee, Won-Jae;Kim, Hee-Cheol;Song, Jin-Ho;Sim, Suk-Ku
    • 한국원자력학회:학술대회논문집
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    • 한국원자력학회 1997년도 추계학술발표회논문집(1)
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    • pp.639-644
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    • 1997
  • The work reported in this paper identifies the thermal-hydraulic phenomena that are expected to occur during a number of key transients in SMART(System-integrated Modular Advanced ReacTor) which is under development at KAERI. The result of this effort is based on the current design concept of SMART integral reactor. Although the design is still evolving, the preliminary phenomena Identification and Ranking Table(PIRT) has been developed based on the experts' knowledge and experience. The preliminary PIRT has been developed by consensus of KAERI expert panelists and AHP(Analytical Hierarchy Process). Preliminary PIRT developed in this paper is intended to be used to identify and integrate development areas of further experimental tests needed, thermal hydraulic models and correlations and code improvements for the safety analysis of the SMART.

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