• 제목/요약/키워드: plant parameters

검색결과 1,822건 처리시간 0.04초

퍼지추론을 이용한 파라미터 식별 및 D.C 서보 모터의 속도제어 (Parameter Identification with Fuzzy Inference and Speed Control of D.C Servo Motor)

  • 이은철;김종훈;이인희;남문현
    • 대한전기학회:학술대회논문집
    • /
    • 대한전기학회 1995년도 하계학술대회 논문집 B
    • /
    • pp.852-854
    • /
    • 1995
  • This paper proposes a new identification method that utilizes fuzzy inference in parameter identification. The prosed system has an additional control loop where a real plant has replaced by a plant model. Fuzzy rules describe the relationship between comparison results of the features and magnitude of modification in the model parameter values. In this paper, the tuning method which determines parameters of PID controller automatically is described through applying this algorithm to DC servo motor. And we intend to investigate effectiveness of the method by experiments. This method is effective in auto-tuning because the response of the closed loop has verified. The simulated and the experimental results of the dc servo motor are shown to confirm the viability of this method.

  • PDF

An Indirect Model Reference Adaptive Fuzzy Control for SISO Takagi-Sugeno Model

  • Cho, Young-Wan;Park, Chang-Woo;Lee, Ki-Chul;Park, Mignon
    • Transactions on Control, Automation and Systems Engineering
    • /
    • 제3권1호
    • /
    • pp.32-42
    • /
    • 2001
  • In this paper, a parameter estimator is developed for the plant model whose structure is represented by the Takagi-Sugeno model. The essential idea behind the on-line estimation is the comparison of the measured stated with the state of an estimation model whose structure is the same as that of the parameterized model. Based on the parameter estimation scheme, and indirect Model Reference Adaptive Fuzzy control(MRAFC) scheme is proposed to provide asymptotic tracking of a reference signal for the systems with uncertain for slowly time-varying parameters. The developed control law and adaptive law guarantee the boundedness of all signals in the closed-loop systems. In addition, the plant state tracks the state of the reference model asymptotically with time for any bounded reference input signal.

  • PDF

Introduction and Expression of Foreign Genes in Rice Cells by Particle Bombardment

  • Jeon, Jong-Seong;Jung, Hou-Sung;Sung, Soon-Kee;Lee, Jong-Seob;Choi, Yang-Do;Kim, Han-Jip;Lee, Kwang-Woong
    • Journal of Plant Biology
    • /
    • 제37권1호
    • /
    • pp.27-36
    • /
    • 1994
  • For establishing a transformation system of rice, an efficient introduction of foreign genes into embryogenic cell suspension by particle bombardment was conducted. The particle inflow gun based on the acceleration of DNA-coated tungsten particles using pressurized helium was constructed for delivery of DNA into rice cells. Several bombardment parameters were optimized using the transient expression of GUS gene. The conditions that gave the highest GUS gene expression of about 1000 blue spots per g fresh weight of bombarded cells include treatment of the cells with 0.5 M osmotic pressure, and use of the 410 kPa helium, 110 mm target distance, 13 mm syringe filter holder and 5 $\mu$L DNA/tungsten mixtures. It was also confirmed that rice actin promoter-intron construct gave the highest expression of all promoter-sequences studied. Eight weeks after the bombardment, stably transformed calluses were obtained on the selection medium containing 100 mg/L G418 and showed the strong activity in in situ GUS assay.

  • PDF

KALMAN FILTER를 이용한 원자로 열출력측정 방법개선에 관한 고찰 (The Study of Improvement in Reactor Thermal Power Measurement Method using KALMAN FILTER)

  • 정남교
    • 기술사
    • /
    • 제30권5호
    • /
    • pp.82-95
    • /
    • 1997
  • A Study of Improvement in Reactor Thermal Power Measurement Method using Kalman Filter. The objectives of the safety analysis of nuclear power plants are to maintain the surface temperature of fuel and fuel cladding within limit value in case of Loss of Coolant accident (LOCA) so that it ensures the safety and reliability of nuclear power plants. The new technique evaluating the reactor power and improvement of existing plant system increase the safety margin of nuclear power plant operation, and accordingly, economic effect will be anticipated. Hereby, 1 would like to introduce reactor power measurement method using Kalman filter that enables to calculate the reactor power more precisely combining the parameters, for example, turbine output as the 1 st stage pressure of high pressure turbine, and reactor power using energy equilibrium relation. It is expected that the new technique will enhance the accuracy of measurement of reactor power and maintain the reliability of nuclear power operation by increasing operational safety margin, and gain the economic benefit

  • PDF

해석적 방법을 이용한 양측식 선형 영구자석 발전기의 특성해석 (Characteristic Analysis of Double sided Permanent Magnet Linear Generator by using Analytical Method)

  • 강한빛;최장영;김경환;홍기용
    • 전기학회논문지
    • /
    • 제63권5호
    • /
    • pp.652-659
    • /
    • 2014
  • This paper deals with characteristic analysis of double sided permanent magnet linear generator using analytical method. We derived magnetic field solutions produced by permanent magnet and armature reaction based on the 2D polar coordinate and magnetic vector potential. based on the derived magnetic field solutions, Induced voltage is obtained when arbitrary sinusoidal input condition. In addition, electrical parameters such as back-EMF constant, resistance, and inductance are obtained. Finally, generating performance characteristic at the rated load and various load is examined by using equivalent circuit.

공압 서보실린더의 신경회로망 결합형 적응제어 (Adaptive Control Incorporating Neural Network for a Pneumatic Servo Cylinder)

  • 장윤성;조승호
    • 대한기계학회논문집A
    • /
    • 제29권1호
    • /
    • pp.88-95
    • /
    • 2005
  • This paper presents a design scheme of model reference adaptive control incorporating a Neural Network for a pneumatic servo system. The parameters of discrete-time model of plant are estimated by using the recursive least square method. Neural Network is utilized in order to compensate the nonlinear nature of plant such as compressibility of air and frictions present in cylinder. The experiment of a trajectory tracking control using the proposed control scheme has been performed and its effectiveness has been proved by comparing with the results of a model reference adaptive control.

DAF(Dissolved Air Flotation)를 이용한 팽화 슬러지 농축 (Thickening of Bulking Sludge using DAF (Dissolved Air Flotation))

  • 김동석;박영식
    • 한국환경과학회지
    • /
    • 제15권1호
    • /
    • pp.77-84
    • /
    • 2006
  • An effective technique of sludge separation is required for excess sludge of sewage or wastewater plant. The separation of bulking sludge of paper manufacturing plant was studied using DAF(Dissolved Air Flotation) system. The effects of parameters such as nozzle type, A/S(air/solid) ratio. pressure, injection time of pressured water and saturation time were examined. The results showed that the best nozzle type was flat which had small orifice hole, The optimum A/S ratio and pressure were $7.070\times10^{-3}$(recycle ratio of pressured water $20\%$) and 5atm, respectively. Injection times of pressurized water around 20-25 sesc and flotation time of 30 min appeared to be optimal for the DAF operation. The order of performance of packing was 18 mm > 22 mm > 32 mm.

680 MW 증기터빈 동적모델 개발 및 속도제어기 검증 (Development of Dynamic Model of 680 MW Rated Steam Turbine and Verification and Validation of its Speed Controller)

  • 최인규;우주희;손기헌
    • KEPCO Journal on Electric Power and Energy
    • /
    • 제5권3호
    • /
    • pp.165-171
    • /
    • 2019
  • The steam turbine used in nuclear power plant is modeled for the purpose of verification of control system rather than the operator education. The valves, reheater and generator are modeled also and integrated into the simulator. After that, the operation data and the designed data such as heat balance diagram are utilized to identify the model parameters. It was evident that model outputs of developed simulator are very close to the measured operating ones. The simulator within dynamic model was used to verify and validate the whole control system together with field instruments. And the target plant has been operating long time.

UNCERTAINTY EVALUATIONS OF CASMO-3/MASTER SYSTEM FOR PWR CORE NEUTRONICS CALCULATIONS

  • Song, Jae-Seung;Kim, Kang-Seog;Lee, Kibog;Park, Jin-Ha;Zee, Sung-Quun
    • 한국원자력학회:학술대회논문집
    • /
    • 한국원자력학회 1996년도 춘계학술발표회논문집(1)
    • /
    • pp.244-250
    • /
    • 1996
  • Uncertainties in core neutronic calculations of CASMO-3/MASTER, which is a KAERI developed core nuclear design code system, were evaluated via comparisons with measured data. Comparisons were performed with plant measurement data from one Westinghouse type and one ABB-CE type plant and two Korean standard type plants. The CASMO-3/MASTER capability and levels of accuracy are concluded to be sufficient for the neutronics design including safety related parameters related with reactivity, power distributions, temperature and power coefficients, inverse boron worth and control bank worth.

  • PDF

Safety Assessment for the Landfill Disposal of Decommissioning Waste Solidified by Magnesium Potassium Phosphate Cement

  • Jeong, Jongtae;Baik, Min-Hoon;Lee, Jae-Kwang;Pyo, Jae-Young;Um, Wooyong;Heo, Jong
    • 방사성폐기물학회지
    • /
    • 제20권1호
    • /
    • pp.13-22
    • /
    • 2022
  • The decommissioning of a nuclear power plant generates large amounts of radioactive waste, which is of several types. Radioactive concrete powder is classified as low-level waste, which can be disposed of in a landfill. However, its safe disposal in a landfill requires that it be immobilized by solidification using cement. Herein, a safety assessment on the disposal of solidified radioactive concrete powder waste in a conceptual landfill site is performed using RESRAD. Furthermore, sensitivity analyses of certain selected input parameters are conducted to investigate their impact on exposure doses. The exposure doses are estimated, and the relative impact of each pathway on them during the disposal of this waste is assessed. The results of this study can be used to obtain information for designing a landfill site for the safe disposal of low-level radioactive waste generated from the decommissioning of a nuclear power plant.