• 제목/요약/키워드: Water-cooled generator

검색결과 54건 처리시간 0.026초

수냉식 대용량 인버터의 방열구조에 따른 냉각효과에 대한 연구 (A Study of the Cooling Effect for a Water-cooled Heat Structure of the Electric Vehicle Inverter System)

  • 김경만;우병국;강찬호;조상준;윤영득;전태원
    • 전력전자학회:학술대회논문집
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    • 전력전자학회 2010년도 추계학술대회
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    • pp.343-344
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    • 2010
  • 화석연료의 고갈로 인하여 친환경 자동차에 대한 연구와 상용화가 급속도로 진행되면서 점점 대형 차종으로 그 범위가 넓어지고 있다. 대형 차종에 적용되는 전기동력 시스템의 MCU(Motor Control Unit), GCU(Generator Control Unit), DC/DC 컨버터 등과 같은 전장품도 그 용량이 커지면서 상용화를 위해 효율적인 측면도 많이 부각되지만 스위칭 소자, 변압기, 초크, 다이오드 등에서 동작으로 인해 열이 발생하고 제품의 구조상 밀폐된 공간에 장착이 되기 때문에 발열로 인한 동작의 신뢰성과 제품의 내구성에 큰 영향을 미치게 된다. 그중 가장 발열이 심한 IGBT(Insulated Gate Bipolar Transistor) 등과 같은 스위칭 소자에서 발생하는 열을 효과적으로 냉각시키기 위해 수냉구조가 필수적이며 동일한 조건의 수압, 유량에 보다 높은 방열특성을 가지기 위해 냉각구조에 대한 해석이 제품을 개발 전에 선행되어야 한다. 본 논문에서는 유로의 냉각핀 형상과 유로 구조에 따라 방열특성이 어떠한 차이가 있는지 시뮬레이션 프로그램을 통하여 비교하고, 모사발열체를 이용한 방열부의 냉각 성능 시험과 다이나모 환경의 최대 출력 시험을 통하여 방열 특성을 확인하였다.

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Multivariate analysis of critical parameters influencing the reliability of thermal-hydraulic passive safety system

  • Olatubosun, Samuel Abiodun;Zhang, Zhijian
    • Nuclear Engineering and Technology
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    • 제51권1호
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    • pp.45-53
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    • 2019
  • Thermal-hydraulic passive safety systems (PSSs) are incorporated into many advanced reactor designs on the bases of simplicity, economics and inherent safety nature. Several factors among which are the critical parameters (CPs) that influence failure and reliability of thermal-hydraulic (t-h) passive systems are now being explored. For simplicity, it is assumed in most reliability analyses that the CPs are independent whereas in practice this assumption is not always valid. There is need to critically examine the dependency influence of the CPs on reliability of the t-h passive systems at design stage and in operation to guarantee safety/better performance. In this paper, two multivariate analysis methods (covariance and conditional subjective probability density function) were presented and applied to a simple PSS. The methods followed a generalized procedure for evaluating t-h reliability based on dependency consideration. A passively water-cooled steam generator was used to demonstrate the dependency of the identified key CPs using the methods. The results obtained from the methods are in agreement and justified the need to consider the dependency of CPs in t-h reliability. For dependable t-h reliability, it is advisable to adopt all possible CPs and apply suitable multivariate method in dependency consideration of CPs among other factors.

저 손실 레디알 전력 결합기와 수냉 시스템을 이용한 고전력 증폭기 구현 (Implementation of a High Power Amplifier using Low Loss Radial Power Combiner and Water Cooling System)

  • 최성욱;김영
    • 한국항행학회논문지
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    • 제22권4호
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    • pp.319-324
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    • 2018
  • 본 논문은 RF 전력 반도체를 사용한 고출력 전력증폭기를 구현한 것으로 기존의 플라즈마 발생 장치에 사용되는 마그네트론 방식의 고출력 증폭기 문제점인 낮은 효율과 짧은 수명, 유지 보수의 어려움 그리고 높은 운용비용 등을 개선하기 위한 것이다. 구현된 고출력 전력증폭기는 2.45 GHz ISM (industrial scientific medical) 대역에서 공간 결합방식을 이용한 저 손실, 고출력 레디알 결합기와 반도체로 3 kW급 출력을 얻기 위해서 300 W 급 전력 증폭기 16개의 증폭기로 구성되어 있다. 또한, 이 증폭기는 개별적인 증폭기에 수냉 방식의 구조를 적용하여 고출력에 따른 발열문제를 극복하였다. 소형 시스템으로 구성된 이 전력증폭기는 원하는 출력에서 50%의 높은 효율을 얻었다.

CONCEPTUAL DESIGN OF THE SODIUM-COOLED FAST REACTOR KALIMER-600

  • Hahn, Do-Hee;Kim, Yeong-Il;Lee, Chan-Bock;Kim, Seong-O;Lee, Jae-Han;Lee, Yong-Bum;Kim, Byung-Ho;Jeong, Hae-Yong
    • Nuclear Engineering and Technology
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    • 제39권3호
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    • pp.193-206
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    • 2007
  • The Korea Atomic Energy Research Institute has developed an advanced fast reactor concept, KALIMER-600, which satisfies the Generation IV reactor design goals of sustainability, economics, safety, and proliferation resistance. The concept enables an efficient utilization of uranium resources and a reduction of the radioactive waste. The core design has been developed with a strong emphasis on proliferation resistance by adopting a single enrichment fuel without blanket assemblies. In addition, a passive residual heat removal system, shortened intermediate heat-transport system piping and seismic isolation have been realized in the reactor system design as enhancements to its safety and economics. The inherent safety characteristics of the KALIMER-600 design have been confirmed by a safety analysis of its bounding events. Research on important thermal-hydraulic phenomena and sensing technologies were performed to support the design study. The integrity of the reactor head against creep fatigue was confirmed using a CFD method, and a model for density-wave instability in a helical-coiled steam generator was developed. Gas entrainment on an agitating pool surface was investigated and an experimental correlation on a critical entrainment condition was obtained. An experimental study on sodium-water reactions was also performed to validate the developed SELPSTA code, which predicts the data accurately. An acoustic leak detection method utilizing a neural network and signal processing units were developed and applied successfully for the detection of a signal up to a noise level of -20 dB. Waveguide sensor visualization technology is being developed to inspect the reactor internals and fuel subassemblies. These research and developmental efforts contribute significantly to enhance the safety, economics, and efficiency of the KALIMER-600 design concept.