• Title/Summary/Keyword: 자속도함수

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Comparison of Rotor Flux Observer Characteristics in Induction Motor Using Parameter Sensitivity (파라미터 민감도를 이용한 유도전동기 회전자 자속관측기의 특성 비교)

  • 최종우;남현택;박용환;김흥근
    • The Transactions of the Korean Institute of Power Electronics
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    • v.7 no.4
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    • pp.377-383
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    • 2002
  • To obtain a high performance in a direct vector controlled induction machine, it is essential to obtain the current rotor flux. The accuracy of flux observers for induction machines inherently depends on parameter sensitivity. This paper proposes an analysis method for conventional flux observers using "parameter sensitivity". The "parameter sensitivity" is defined as the ratio of the percentage change in the system transfer function to the percentage change of the parameter variation. We define the ratio between real flux and estimated no as the transfer function, and analyze a parameter sensitivity of this transfer function. Practical verification is presented to conform the capabilities of the proposed analysis method.sed analysis method.

A Rotor Speed Estimation of Induction Motors Using Sliding Mode Cascade Observer (슬라이딩 모드 축차 관측기를 이용한 유도 전동기 속도추정)

  • 김응석
    • The Transactions of the Korean Institute of Electrical Engineers D
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    • v.53 no.3
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    • pp.145-153
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    • 2004
  • A nonlinear adaptive speed observer is designed for the sensorless control of induction motors. In order to design the speed observer, the measurements of the stator currents and the estimates of the rotor fluxes are used. The sliding mode cascade observer is designed to estimate the time derivatives of the stator currents. The open-loop observer is designed to estimate the rotor fluxes and its time derivatives using the stator current derivatives. The adaptive observer is also designed to estimate the rotor resistance. Sequentially, the rotor speed is calculated using these estimated values. It is shown that the estimation errors of the corresponding states and the parameters converge to the specified residual set. It is also shown that the speed controller using these estimates is performed well. The simulation examples are represented to investigate the validity of the proposed observers for the sensorless control of induction motors.

무부하운전시의 철극동기기의 3상단락

  • 이면영
    • 전기의세계
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    • v.10
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    • pp.55-61
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    • 1963
  • 본 논문에서 취급한 제동권선이 없는 철극선의 3상단락현상을 해명하는데 있어 우선 임의력율의 전류를 횡축분과 직축분으로 분리해서 취급하는 소위 Blonde의 2반작용법(two reaction method)를 썼고, 각종 Reactance를 표시하는데는 편리한 단위법(perunit notation)을 사용했으며, 전기자의 1상저항은 각종 Reactance ( $X_{x}$, $X_{q}$ )의 어느것 보담도 극소치임으로 실제계산에는 무시했으나 과도전류의 변화를 좌우하는 감쇠정수[decrement factor)에는 큰 영향을 준다는 것이 규명되었다. 해석결과로서 3상단락전류의 초기치는 특수치보다 훨씬 큰 이유로서 단락전류가 계자자속을 약하게 만들어 그 반동으로 계자회로에 일정자속을 유지하기 위하여 부문적으로 개자전류가 증대함을 알게되었고, 단락전류의 직축분과 횡축분의 구성분이 규명검토되었고, 발전기의 돌발단락저류는 일반적으로 직류분, 기본파교류분 및 제2조파등을 포함하나 그 전부가 시정수의 역수인 감쇠정수에 지배되어서 지수함수곡선에 따라 감쇠되어 결국에는 지속단락전류에 귀착한다는 사실과 3상단락은 평형단락사고임으로 영상전류는 영이며 각상과도전류의 위상차가 120.deg.라는 것엔 변함이 없다는 것과 끝으로 철극기를 정격속도로 운전해 놓고 이것을 여자해서 무부하전압을 수기시켜 그의 3상전단자를 돌연 단락해서 그의 과도전류의 파형을 Oscillograph로 촬영하면 본론에서 해석한 결과식의 그것과 일치하게 됨을 알 수 있을 것이다.것이다.

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Exciter Pole Design and Analysis of WPM using Response Surface Method (반응표면법을 이용한 WPM의 exciter pole 설계 및 해석)

  • Yuk, Kyeong-Jin;Park, Gwan-Tae;Lee, Gyu-Jong;Kim, Byung-Taek
    • Proceedings of the KIEE Conference
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    • 2011.07a
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    • pp.916-917
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    • 2011
  • 본 논문에서는 WPM의 기동시 감자된 영구자석을 착자시키는 exciter pole의 최적설계에 대해 다룬다. 영구자석형 동기전동기의 성능을 결정짓는 자석의 잔류자속밀도를 최대로 만들기 위하여 반응표면법을 이용하여 exciter를 설계하였다. 목적함수는 영구자석 중심에서 의 자계의 세기이며 정밀도를 위하여 유한요소법을 통해 결과를 확인하였다.

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A Study on the Electrochemical Properties of SPEEK/PWA/Silica Composite Membranes (SPEEK/PWA/Silica 복합막의 전기화학적 특성에 관한 연구)

  • Oh, Sae-Joong
    • Journal of the Korea Academia-Industrial cooperation Society
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    • v.14 no.5
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    • pp.2529-2535
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    • 2013
  • Sol-gel method was utilized to prepare SPEEK/PWA electrolyte composite membranes. TEOS was used as a precursor and phosphotungstic acid(PWA) as a catalyst for the sol-gel reaction. It was observed through FE-SEM analysis that the PWA and silica nanoparticles were uniformly dispersed into the polymer matrix. The water uptake of SPEEK/PWA/silica composite membranes was less affected by TEOS concentration at higher TEOS contents, while the water uptake decreased as TEOS concentration increased at lower TEOS contents. The proton conductivity of the composite membranes showed similar trend as the water uptake of the composite membranes. The methanol permeability of SPEEK/PWA/silica composite membranes decreased as TEOS concentration increased.

The In-Core Fuel Management by Variational Method (변분법에 의한 노심 핵연료 관리)

  • Kyung-Eung Kim
    • Nuclear Engineering and Technology
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    • v.16 no.4
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    • pp.181-194
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    • 1984
  • The in-core fuel management problem was studied by use of the calculus of variations. Two functions of interest to a public power utility, the profit function and the cost function, were subjected to the constraints of criticality, the reactor turnup equations and an inequality constraint on the maximum allowable power density. The variational solution of the initial profit rate demonstrated that there are two distinct regions of the reactor, a constant power region and a minimum inventory or flat thermal flux region. The transition point between these regions is dependent on the relative importance of the profit for generating power and the interest charges for the fuel. The fuel cycle cost function was then used to optimize a three equal volume region reactor with a constant fuel enrichment. The inequality constraint on the maximum allowable power density requires that the inequality become an equality constraint at some points in the reactor. and at all times throughout the core cycle. The finite difference equations for reactor criticality and fuel burnup in conjunction with the equality constraint on power density were solved, and the method of gradients was used to locate an optimum enrichment. The results of this calculation showed that standard non-linear optimization techniques can be used to optimize a reactor when the inequality constraints are properly applied.

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The Sensorless Control of PMSM Using the Coordinate Transform and Differential Method (좌표 변환과 미분 기법을 이용한 PMSM의 센서리스 제어)

  • Choi, Chul;Won, Tae-Hyun;Park, Sung-Jun;Park, Han-Woong;Kim, Chul-Woo
    • The Transactions of the Korean Institute of Power Electronics
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    • v.8 no.2
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    • pp.107-115
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    • 2003
  • PMSM(permanent magnet synchronous motor) are widely used in industrial and home appliance because of their high torque to inertia ratio, superior power density, and high efficiency For the high control performance, accurate information of rotor position Is essential. In recent, sensorless algorithms are much studied due to high cost problem of position sensor and low reliability in harsh environment. In the proposed method, a differential linkage flux is used for the estimation of rotor position. The differential magnetic field flux is calculated by the voltage equations and measured phase current without any integration and differential calculus. Instead of linkage flux calculation with differential operation, a new mathematical differential method is introduced by a-$\beta$ transformation. The proposed novel position sensorless speed control scheme is verified through experimental results.

Design of a AC Magnetic Leakage Flux Scan System use in DSP (DSP를 이용한 교류누설 자속 탐상 시스템의 설계)

  • 임형석;이영훈
    • Journal of the Korea Society of Computer and Information
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    • v.8 no.4
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    • pp.75-80
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    • 2003
  • In this paper, we designed add current scan system basically. Although NDT system using AC method in now days had problem with limit of detection rate and limit of device organization, in this paper, we made up these problem so that designed device smaller than system used, reduction of cost of system organization and precision of measuring crack. Also, AC leakage flux system had high accuracy about minute crack in the surface and advantage of designing system easily so that we designed system for concerning about crack of surface. Furthermore, it can be able to detect exact crack of reference in wide area by using DSP320C31 chip to reduce the time of measuring crack.

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A Numerical Model for Predicting the Radial Power Profile in CANDU-PHWR Fuel Pellet (CANDU-PHWR 핵연료 소결체의 반경방향 출력분포 수치모형)

  • Woan Hwang;Suk, Ho-Chun;Jae, Won-Mok
    • Nuclear Engineering and Technology
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    • v.23 no.4
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    • pp.444-455
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    • 1991
  • An accurate and fast running NEDAR model for calculating radial power profile throughout fuel life in both solid and annular pellets for existing and advanced CANDU-PHWR-fuel was developed in this work. This model contains resultant flux depression equations and neutron depression data tables which have been developed for CANDU-PHWR fuel of pellet with the diameter 8.0 to 19.5 mm and enrichment 0.71-6.0 wt % U-235, over a bumup range of 0 to 840 MWh /kgU (35000 MWD/T). In order to obtain the neutron flux distribution in the fuel pellet, the CE-HAMMER physics code was run for a neutron flux spectrum appropriate to a CANDU-PHWR to give predictions of radial power profile for several ranges of fuel design parameters. The results, which were calculated by the CE-HAMMER physics code, were fitted to an equation which is solved in terms of Bessel and exponential functions in order to obtain the parameters, $textsc{k}$, $\beta$ and λ in the resultant equation. The present NEDAR model produce a radial profile which, when normalized to unity at the pellet surface, is slightly higher than the profile of the original ELESIM data table. The predictions of the fission gas release by KAFEPA-NEDAR are in slightly better agreement with the experiments than those of ELESIM. The NEDAR model described in this study has been shown to provide an effective, reliable, and accurate method for determining radial power profiles in CANDU-PHWR fuel rods without incurring a significant increase in computing time.

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Investigation on the Allowable Transient Power Levels to Maintain the Mechanical Integrity of the 17$\times$17 KOFA Fuel Rod During the ANS Conditions I and II (ANS과도조건 I 및 II에서 17x17 KOFA 핵연료봉의 기계적 건전성이 유지되는 과도상태 허용 출력준위에 관한 연구)

  • Lee, Chan-Bock;Kim, Ki-Hang;Kim, Kyu-Tae
    • Nuclear Engineering and Technology
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    • v.26 no.1
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    • pp.119-125
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    • 1994
  • Transient power level of the fuel rod is one of the key parameters for the transient fuel behavior. Through the analysis of the fuel performance data bases and sensitivity analyses of such parameters as rod power history, fast neutron flux, fuel enrichment and cycle length, which can affect the transient fuel behavior, a methodology generally applicable to find the allowable transient power level during the ANS Conditions I and II below which the mechanical integrity of the fuel rod is maintained was derived, and allowable transient power levels for the 17$\times$17 KOFA fuel rod have been determined as a function of the burnup. With the introduction of this methodology, design analysis of the transient fuel behavior currently being calculated every cycle can be replaced by the simple check of the peak transient power level achievable during the cycle, and an operational flexibility of the reactor can be obtained by allowing higher transient power level up to 689.5 w/cm at low burnup range than current maximum allowable transient power level, 591 w/cm for the 17$\times$17 KOFA fuel.

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