• 제목/요약/키워드: Fuel-C

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마이크로포커스 X-선 투과 영상을 이용한 모의 TRISO 핵연료 입자 코팅 층 두께 비파괴 측정 (Nondestructive Measurement of the Coating Thickness in the Simulated TRISO-Coated Fuel Particle Using Micro-Focus X-ray Radiography)

  • 김웅기;이영우;박지연;박정병;나성웅
    • 비파괴검사학회지
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    • 제26권2호
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    • pp.69-76
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    • 2006
  • 차세대 원자로로 부각되고 있는 고온가스로에서는 윈자로에서는 고온 안정성 및 핵분열생성물 차단 성능이 우수한 TRISO(tri-isotropic) 핵연료를 사용하고 있다. TRISO 핵연료 입자는 직경이 약 1mm인 구 형태로 입자의 중심에는 직경 0.5mm의 핵연료 커널(kernel)이 포함되며 커널 외곽을 코팅 층이 에워싸고 있다. 이 코팅 층은 완충(buffer) PyC(pyrolytic carbon)층, 내부 PyC층, SiC층, 그리고 외부 PyC층으로 구성되어 있다. 각 코팅 층의 두께는 수십-백${\mu}m$ 범위이고 사양으로 정해져 있으며, 본 연구에서는 각 코팅 층의 두께를 비파괴적으로 측정하기 위하여 마이크로포커스 X-선 발생장치와 고해상도 X-선 평판(flat panel) 검출기초 구성된 정밀한 X-선 래디오그래피 장치를 개발하였다. 개발된 마이크로 X-선 래디오그래피 장치를 이용하여 $UO_2$ 핵물질 $ZrO_2$를 커널로 사용한 모의 TRISO 핵연료 입사에 대한 투과 영상을 획득한 후 디지털 영상처리 기술을 이용하여 코팅 층 사이의 경계선이 구분 가능하도록 영상을 개선하고 디지털 영상처리 알고리듬을 개발하여 코팅 층의 두께를 파동으로 측정하였다.

연료유 가열이 디젤기관의 연소특성 및 기관성능에 미치는 영향에 관한 연구 (A Study on the Effects of Heating of Fuel Oil on Combustion Characteristics and Engine Performance)

  • 고대권
    • 수산해양기술연구
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    • 제25권2호
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    • pp.82-86
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    • 1989
  • 국산 소형어선용 예연소실식 디젤기관의 연료유를 가열할 경우, 연소특성 및 기관성능에 미치는 영향에 관하여 실험한 결과를 요약하면 다음과 같다. 1) 연료유 분사시작점은 연료유 가열온도의 증가에 따라 늦어지는 경향을 나타냈으며, 특히 저부하 운전시 늦어지는 경향이 현저했다. 2) 연소최고압력점은 연료유 가열온도의 증가에 따라 늦어졌으며, 연소최고압력은 연료유 가열온도 증가에 따라 감소하였으나 부하의 증가에 따라 증가하는 경향을 나타내었다. 3) 연료소비율은 부하의 증가에 따라 감소하였으며, 연료소비율이 가장 작은 연료유의 최적가열온도는 15$0^{\circ}C$부근임을 나타내고 있다. 4) 그을음농도는 부하와 연료유 가열온도의 증가에 따라 증가하는 경향을 나타냈다.

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Characteristics of the Multi-kW Class Polymer Electrolyte Membrane Fuel Cell Stack for a Hybrid Electric Golf Cart

  • I.H. Oh;S.J. Shin;J.H. Jo;Park, S.K.;H.Y. Ha;S.A. Hong;S.Y. Ahn;Lee, Y.C.;S.A. Cho
    • 에너지공학
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    • 제11권3호
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    • pp.254-261
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    • 2002
  • The fabrication method for the main components of the polymer electrolyte membrane fuel cell stack such as electrodes, membrane-electrode assemblies, and bipolar plates was established for the effective electrode area of 240 ㎠. A counter-flow type 100-cell stack was fabricated by using the above components and then a maximum power of 7.44 kW for H$_2$/O$_2$ and 5.56 kW for H$_2$/air could be obtained at 70$\^{C}$ and 1 atm. It was seen that the distribution of the OCV for unit cells in the stack was uniform but the voltage deviation increased as the load increased due to the IR drop and the electrode polarization. The stack was applied to the power source of the fuel cell/battery hybrid electric golf car. It produced about 1 kW at a room temperature operation during the test run, which occupied about 43% of the total power required by the 2.3 kW motor.

FARE Device Operational Characteristics of Remote Controlled Fuelling Machine at Wolsong NPP

  • I. Namgung;Lee, S.K.;Kim, Y.B.
    • Nuclear Engineering and Technology
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    • 제34권5호
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    • pp.468-481
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    • 2002
  • There are 4 CANDU6 type reactors operating at Wolsong site. For fuelling operation of certain fuel channels (with flow less than 21.5 kg/s) a FARE flow Assist Ram Extension) device is used. During the refuelling operation, two remote controlled F/Ms (Fuelling Machines) are attached to a designated fuel channel and carry out refuelling job. The upstream F/M inserts new fuel bundles into the fuel channel while the downstream F/M discharges spent fuel bundles. In order to assist fuelling operation of channels that has lower coolant How rate, the FARE device is used instead of F/M C-ram to push the fuel bundle string. The FARE device is essentially a How restricting element that produces enough drag force to push the fuel bundle string toward downstream F/M. Channels that require the use of FARE device for refuelling are located along the outside perimeter of reactor. This paper presents the FARE device design feature, steady state hydraulic and operational characteristics and behavior of the device when coupled with fuel bundle string during fuelling operation. The study showed that the steady state performance of FARE device meets the design objective that was confirmed by downstream F/M C-ram force to be positive.

Effect of UO2+x Powders Produced at Different Oxidation Temperatures on the Properties of Pellet

  • Yoo, Ho-Sik;Lee, Seung-Jae;Kim, Jae-Ik;Song, Kun-Woo
    • 한국세라믹학회지
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    • 제40권5호
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    • pp.410-414
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    • 2003
  • Characteristics of $UO_{2+x}$ powders oxidized at different temperatures were examined. Pellets were fabricated by adding these oxidation powders and their properties were also investigated. Particle size of the $UO_{2+x}$ powders decreased with increasing oxidation temperature while surface area increased. Only the powders oxidized at 35$0^{\circ}C$ enhanced the strength of green pellet. However, 35$0^{\circ}C$ oxidized powders added pellet had many surface defects. The difference of shrinkage rate between the oxidized and UO$_2$ powders was thought to be the cause of them.

초음파 조사 디젤유 적용 커먼레일 디젤기관 특성에 관한 연구 (Study on the Characteristics of Common-rail Diesel Engine with Ultrasoniccally Irradiated Diesel Fuel)

  • 임석연;정영철;조성철;류정인
    • 한국분무공학회지
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    • 제11권2호
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    • pp.69-74
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    • 2006
  • This is an experimental study on the performance characteristics and combustion characteristics of common-rail type diesel engine by using ultrasonic energy. It is carried out engine performance by engine dynamometer test and combustion characteristics using ultrasonically irradiated diesel fuel in comparison with using conventional diesel fuel. In analyzing the experiments of these results generally, these are obtained as follows. There is an affirmative effect on the side of the improvement of power and the reduction of smoke by applying the ultrasonically irradiated diesel fuel to the common rail engine. But there is less effect on the side of improvement of BSFC.

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세라믹 멤브레인 활용 직접 에탄올 연료전지 (Direct Ethanol Fuel Cell (DEFC) Fabricated with Ceramic Membrane)

  • 정재근;윤영훈
    • 한국수소및신에너지학회논문집
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    • 제25권4호
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    • pp.419-424
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    • 2014
  • Direct ethanol fuel cell has been fabricated with ceramic membrane. A porous silicon carbide (SiC) membrane having approximately 30% porosity has been applied for a direct ethanol proton exchange membrane (DE-PEM) fuel cell. A horizontal type cell having Pt ($18mg/cm^2$) catalyst layer on both side of the ceramic membrane was used for the demonstration test. The ethanol oxidation based-fuel cell stack showed very high voltage (1.289V) and measurable current level (68mA) even though at room temperature.

코팅과 열처리가 연료전지 분리판의 내식성에 미치는 영향 (Effect of the Coaling and Annealing on Noncorrosive of Fuel Cell Separator)

  • 김귀열
    • 한국전기전자재료학회논문지
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    • 제20권11호
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    • pp.1000-1003
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    • 2007
  • The molten carbonate fuel cell has conspicuous feature and high potential in being used as an energy converter of various fuel to electricity and heat. However, the molten carbonate fuel cell which use strongly corrosive molten carbonate at $650^{\circ}C$ have many problem. One of the material problems is the severe corrosion of the metallic components, such as the separator. The effect of coating and annealing treatment on the corrosion for SUS 304 and SUS 430 which are the candidate materials for molten carbonate fuel cell hardware has been investigated in molten carbonate at $650^{\circ}C$ by using steady state polarization and electrochemical impedance spectroscopy method. It was found that the corrosion current of these SUS 304 and SUS 430 decreased with coating and annealing treatment.

Structural Analysis of CANFLEX Fuel Bundles

  • H. Y. Kang;K. S. Sim;Lee, J. H.;Kim, T. H.;J. S. Jun;C. H. Chung;Park, J. H.;H. C. Suk
    • 한국원자력학회:학술대회논문집
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    • 한국원자력학회 1995년도 추계학술발표회논문집(2)
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    • pp.1008-1013
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    • 1995
  • The CANFLEX fuel bundle has been developed by KAERI/AECL jointly to facilitate the use of various fuel cycles in CANDU-6 reactor. As one of the design evaluations, the structural analysis of the fuel bundles by hydraulic drag force is performed to evaluate the fuel integrity in the period of the refuelling in CANDU-6. The structural integrity is evaluated by FEM modelling for the complicated bundles configuration in channel. It is noted that the present analysis method is newly developed for the structural integrity evaluation. The analysis results show that the fuel bundle is shown to keep its structural integrity during the refuelling.

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Initial Release of Nuclides from Spent PWR Fuels

  • Kim, S. S.;K. S. Chun;Kim, Y. B.;Park, J. W.
    • 한국방사성폐기물학회:학술대회논문집
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    • 한국방사성폐기물학회 2004년도 Proceedings of the 4th Korea-China Joint Workshop on Nuclear Waste Management
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    • pp.238-244
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    • 2004
  • The relationship between the leaching and gap inventory of spent fuel has been studied. When a specimen of J44H08 spent PWR fuel with 38 GWD/MTU has been leached in the synthetic granitic groundwater in Ar atmosphere, the released fraction of cesium was increased rapidly up to 0.7% at around 500 days and stayed below 0.8% until 3 years. This 0.7% of cesium might be released from the gap in this fuel. The measurement of gap inventory with C15I08 spent PWR fuel, having 35 GWD/MTU and 0.22% of fission gas release, was also determined near 0.6% for the cesium, which is a similar fraction of cesium released from the leaching experiment with J44H08 fuel. Its gap inventories of strontium and iodine were about 0.03 and less than 0.2% respectively. Respective fractions of cesium and strontium in grain boundary of C15I08 were 0.78, 0.09%.

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