• Title/Summary/Keyword: E-J power

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Novel Single-Stage Power Factor Correction AC/DC Converter with Low DC Link Voltage using New Magnetic Feedback Technique (새로운 마그네틱 피드백 기법을 이용하여 낮은 링크 전압을 갖는 새로운 단일 전력단 역률 개선 AC/DC 컨버터)

  • Choi E. S.;Yoon H. K.;Kim C. E.;Moon G. W.;Youn M. J.
    • Proceedings of the KIPE Conference
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    • 2004.07b
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    • pp.528-532
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    • 2004
  • Novel single-stage power factor correction AC/DC converter with low DC link voltage using new magnetic feedback technique is proposed in this paper. The Proposed converter has high power factor, tight output voltage regulation and low link capacitor voltage less than 450V for all the load range through the universal input line. This converter has also no dead-zone in the input current, which is seen in the conventional converter using the previous magnetic feedback technique. In this paper, the analysis of operations and features of the proposed converter is provided, and the experimental results of 90W-prototype shows the low harmonic distortions satisfied with EN 61000-3-2 Class D, high power factor and low link voltage less than 450V.

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Charicteristics of HF 10-cm Type Grid Ion Source for Inert and Chemically Reactive Gases.

  • Chol, W.K;Koh, S.K;Jang, H.G;Jung, H.J;Kondranin, S.G.;Kralkina, E.A.;Bougrov, G.E.
    • Proceedings of the Korean Vacuum Society Conference
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    • 1996.02a
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    • pp.102-102
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    • 1996
  • This paper represents a new type low power High Frequency technological ion source (HF TIS) for ion - beam processing: the surface modification of materials, cleaning of surface, sputtering, coating of thin films, and polishing. The operational principle of HF TIS is based on the excitation of electrostatic waves in plasma located in the external magnetic field. Low power HF TIS with diameter 92 rom gives the opportunity to obtain beams of inert and chemically reactive gases with currents range from 5 to 150 mA (current density $0.015\;~\;3.5\;mA/\textrm{m}^2$) and ion beam energy 100 ~ 2500 eV at a HF power level 10 ~ 150 W. Three grid concave type ion optical system (IOS) is used for extraction and formation ofion beam.n beam.

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Impulse Response Characteristics of the Grounding Systems with respect to the Common-Connection Position in Power Utility System (수변전설비에서 접지시스템의 공결점의 위치에 따른 임펄스 응답특성)

  • Lee, B.H.;Eom, J.H.;Kim, S.W.;Shim, P.S.;Lee, S.C.
    • Proceedings of the KIEE Conference
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    • 1999.07e
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    • pp.2149-2151
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    • 1999
  • This paper describes the impulse response characteristics of the grounding systems in power utility system. Several regulations regarding to electric power equipments, services and managements require that the groundings of class 1 ($E_1$) and class 2 ($E_2$) must be connected at the common point in grounding systems. In addition, the grounding for arrester ($E_{LA}$), which belongs to the grounding of class 1, should be connected at the same point. However, there is no method and position of common-connection at anywhere. In this work, when the impulse current was injected through the grounding conductor for arrester, the investigations measuring and analyzing potential rises induced at the common connection point and other grounding conductors were conducted. The experiments were carried out in the conditions of the grounding conductor of 25m long and the near or remote common connection from ground electrode. The lightning impulse current was applied so as to simulate the on-set of arrester due to lightning and/or switching surges.

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Implementation of Strength Pareto Evolutionary Algorithm II in the Multiobjective Burnable Poison Placement Optimization of KWU Pressurized Water Reactor

  • Gharari, Rahman;Poursalehi, Navid;Abbasi, Mohammadreza;Aghaie, Mahdi
    • Nuclear Engineering and Technology
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    • v.48 no.5
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    • pp.1126-1139
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    • 2016
  • In this research, for the first time, a new optimization method, i.e., strength Pareto evolutionary algorithm II (SPEA-II), is developed for the burnable poison placement (BPP) optimization of a nuclear reactor core. In the BPP problem, an optimized placement map of fuel assemblies with burnable poison is searched for a given core loading pattern according to defined objectives. In this work, SPEA-II coupled with a nodal expansion code is used for solving the BPP problem of Kraftwerk Union AG (KWU) pressurized water reactor. Our optimization goal for the BPP is to achieve a greater multiplication factor ($K_{eff}$) for gaining possible longer operation cycles along with more flattening of fuel assembly relative power distribution, considering a safety constraint on the radial power peaking factor. For appraising the proposed methodology, the basic approach, i.e., SPEA, is also developed in order to compare obtained results. In general, results reveal the acceptance performance and high strength of SPEA, particularly its new version, i.e., SPEA-II, in achieving a semioptimized loading pattern for the BPP optimization of KWU pressurized water reactor.

An Experimental Study on the Small Capacity EHD Power Generation (소용량 EHD 발전에 관한 실험적 연구)

  • Jhoun, C.S.;Lee, J.B.;Lim, E.C.
    • Solar Energy
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    • v.9 no.2
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    • pp.58-68
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    • 1989
  • This paper describes an experimental study that was performed to determine the limiting factors on the power output in the closed cycle Electro-Hydro-Dynamic generator of small capacity. A corona discharge for producing unipolar charged particles used as the charging method. The experiment demonstrated that the corona method of charging was an efficient and effective means of producing unipolar charged particles. Four factors having an effect on the power output characteristics of EHD generator are discussed and examined experimentally, using methyl alcohol and kerosene as working fluides; a. The conversion length between attractor and collector. b. The corona current of Emitter. c. The flow velocity of working fluids. d. Load resistance. This results are as follows; 1) There in a critical value in conversion length for its maximum power output. 2) Power output increases almost linearly with corona current and flow velocity. 3) There is the critical value of load resistance producing a maximum power output. 4) Kerosene is known better working fluid than Methyl alcohol in this EHD generator.

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The analysis result of temporary operation of 765 kV transmission line as 345 kV rating (765 kV 송전선로의 345 kV 운전에 따른 계통 해석)

  • Woo, J.W.;Shim, E.B.;Kang, Y.W.
    • Proceedings of the KIEE Conference
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    • 1998.07e
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    • pp.1647-1649
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    • 1998
  • This paper describes the power frequency voltage and its countermeasure when a 765 kV transmission line is directly connected to a 345 kV line and operated at 345 kV voltage. The summary of this result is as follows : The western route of 765 kV transmission line doesn't need any countermeasure to reduce the power frequency voltage at the receiving end. The eastern route of 765 kV transmission needs 100 Mvar(3 phase) capacity of shunt reactor at the receiving end to reduce the power frequency voltage. The use of shunt reactors in the 765 kV transmission lines has unexpected problems, one of which is induction of high voltages on a de-energized circuit of two parallel lines. This paper examined the problem of resonance on two parallel transmission circuits in one routes.

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Performance Model and Fuel Utilization Analysis of 7 kW MCFC using ASPEN-PLUS (ASPEN-PLUS를 이용한 7 kW MCFC의 성능 모델 및 연료 이용률 분석)

  • Kang, B.S.;Ahn, K.S.;Koh, J.H.;Lim, H.C.
    • Proceedings of the KIEE Conference
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    • 1998.07a
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    • pp.55-57
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    • 1998
  • Molten carbonate fuel cell (MCFC) power plant is expected to be one of the most promising future power generation system for the electric utilities because of its high efficiency, environmental suitability and capability of using coal as fuel. To get such attractive performance, it is necessary to consider optimizing operation and gas recycling system. This paper describes the simulation results of 7 kW MCFC stack in KEPRI and the effects of the three possible gas recycling operations, i.e. cathode gas recycling, anode gas recycling, anode gas recycling with catalytic burner.

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Development of a human reliability analysis (HRA) guide for qualitative analysis with emphasis on narratives and models for tasks in extreme conditions

  • Kirimoto, Yukihiro;Hirotsu, Yuko;Nonose, Kohei;Sasou, Kunihide
    • Nuclear Engineering and Technology
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    • v.53 no.2
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    • pp.376-385
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    • 2021
  • Probabilistic risk assessment (PRA) has improved its elemental technologies used for assessing external events since the Fukushima Daiichi Nuclear Power Station Accident in 2011. HRA needs to be improved for analyzing tasks performed under extreme conditions (e.g., different actors responding to external events or performing operations using portable mitigation equipment). To make these improvements, it is essential to understand plant-specific and scenario-specific conditions that affect human performance. The Nuclear Risk Research Center (NRRC) of the Central Research Institute of Electric Power Industry (CRIEPI) has developed an HRA guide that compiles qualitative analysis methods for collecting plant-specific and scenario-specific conditions that affect human performance into "narratives," reflecting the latest research trends, and models for analysis of tasks under extreme conditions.

A Study on the 43$0^{\circ}C$ Degradation Behavior of Cast Stainless Steel(CF8M) (III) - Evaluation of Elastic-Plastic Fracture Toughness - (주조 스테인리스강 CF8M의 43$0^{\circ}C$ 열화거동에 관한 연구 (III) - 탄소성 파괴인성 평가 -)

  • Gwon, Jae-Do;In, Jae-Hyeon;Park, Jung-Cheol;Choe, Seong-Jong;Park, Yun-Won
    • Transactions of the Korean Society of Mechanical Engineers A
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    • v.24 no.10 s.181
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    • pp.2405-2412
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    • 2000
  • A cast stainless steel may experience an embrittlement when it is exposed to approximately 30$0^{\circ}C$ for long period. In the present investigation, The three classes of the thermally aged CF8M specimie n are prepared using an artificially accelerated aging method. Namely, after the specimen are held for 300, 1800 and 3600hrs. at 43$0^{\circ}C$ respectively, the specimens are quenched in water to room temperature. Load versus load line displacement curves and J-R curves are obtained using the unloading compliance method. $J_{IC}$ values are obtained following ASTM E 813-87 and ASTM E 813-81 methods. In addition to these methods, JIC values are obtained using SZW(stretch zone width) method described in JSME S 001-1981. The results of the unloading compliance method are $J_Q$=485.7 kJ/m$^2$ for virgin material, $J_{IC}$ of the degraded materials associated with 300, 1800 and 3600hrs are obtained 369.25 kJ/m$^2$, 311.02 kJ/m$^2$, 276.7 kJ/m$^2$, respectively. The results of SZW method are similar to those of the unloading compliance method. Through the elastic-plastic fracture toughness test, it is found that the value of $J_{IC}$ is decreased with increasing of the aging time. The results obtained through the investigation can provide reference data for a leak before break(LBB) of reactor coolant system of nuclear power plants.

Development of a Test Apparatus for Control Element Drive Mechanism of Standard Reactor (표준형 원자로 제어봉 구동장치 시험기기 개발)

  • Kim, C.K.;Cheon, J.M.;Lee, J.M.;Kweon, S.M.
    • Proceedings of the KIEE Conference
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    • 2004.07d
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    • pp.2374-2376
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    • 2004
  • In this paper, we describe a DSP-based test apparatus for Control Element Drive Mechanism (CEDM). Using this apparatus, we can catch the mechanical and electrical characteristics of CEDM and obtain the information about the improvement of CEDM and the design of CEDM power controller. The test apparatus for CEDM introduced in this paper can input firing angles directly into gate drive circuits of thyristors so that this method can be used to derive the maximum and minimum values of firing angles within available limits for a 3-phase half-wave rectifier. Angle inputs help us understand each coil's response characteristics. Since this apparatus generates a serial sequence for CEDM insertion and withdrawal operations, we may judge whether CEDM works correctly as expected or not in each phase of a step movement.

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