• Title/Summary/Keyword: Fuel-C

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Analysis of Thermal Shock Behavior of Cladding with SiCf/SiC Composite Protective Films (SiCf/SiC 복합체 보호막 금속피복관의 열충격 거동 분석)

  • Lee, Dong-Hee;Kim, Weon-Ju;Park, Ji-Yeon;Kim, Dae-Jong;Lee, Hyeon-Geon;Park, Kwang-Heon
    • Composites Research
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    • v.29 no.1
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    • pp.40-44
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    • 2016
  • Nuclear fuel cladding used in a nuclear power plant must possess superior oxidation resistance in the coolant atmosphere of high temperature/high pressure. However, as was the case for the critical LOCA (loss-of-coolant accident) accident that took place in the Fukushima disaster, there is a risk of hydrogen explosion when the nuclear fuel cladding and steam reacts dramatically to cause a rapid high-temperature oxidation accompanied by generation of a huge amount of hydrogen. Hence, an active search is ongoing for an alternative material to be used for manufacturing of nuclear fuel cladding. Studies are currently aimed at improving the safety of this cladding. In particular, ceramic-based nuclear fuel cladding, such as SiC, is receiving much attention due to the excellent radiation resistance, high strength, chemical durability against oxidation and corrosion, and excellent thermal conduction of ceramics. In the present study, cladding with $SiC_f/SiC$ protective films was fabricated using a process that forms a matrix phase by polymer impregnation of polycarbosilane (PCS) after filament-winding the SiC fiber onto an existing Zry-4 cladding tube. It is analyzed the oxidation and microstructure of the metal cladding with $SiC_f/SiC$ composite protective films using a drop tube furnace for thermal shock test.

A Study on the Spray and Fuel-Film Formation Mechanism of MPI Injector (다점 분사식 인젝터의 분무 및 벽류 생성 과정에 관한 연구)

  • Lee, K.H.;Lee, C.S.;Kim, B.K.;Sung, B.K.
    • Journal of ILASS-Korea
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    • v.1 no.2
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    • pp.33-41
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    • 1996
  • Mixture formation is one of the important factors to improve combustion performance of MPI gasoline engines. This is affected by spray and atomization characteristics of injector. Especially, in the case of EGI system, air-fuel mixing period is too short and formed a lot of fuel-film in the intake manifold and cylinder wall. This fuel-film is not burnt in cylinder, it is exhausted in the form of HC emission. In this paper, spray characteristics such as size distributions, SMD, and spray angle are measured by PMAS, and the fuel-film measuring device is developed specially. Using this device, the amount and distribution of fuel-film which flows into through valve can be measured Quantitatively. As the result of these experiments, the information of optimal spray characteristics and injection condition that minimize the fuel-film can be built up.

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OPERATION ALGORITHMS FOR A FUEL CELL HYBRID ELECTRIC VEHICLE

  • PARK C.;KOOK K.;OH K.;KIM D.;KIM H.
    • International Journal of Automotive Technology
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    • v.6 no.4
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    • pp.429-436
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    • 2005
  • In this paper, operation algorithms are evaluated for a fuel cell hybrid electric vehicle (FCHEV). Power assist, load leveling and equivalent fuel algorithm are proposed and implemented in the FCHEV performance simulator. It is found from the simulation results that the load leveling algorithm shows poor fuel economy due to the system charge and discharge efficiency. In the power assist and equivalent fuel algorithm, the fuel cell stack is operated in a relatively better efficiency region owing to the battery power assist, which provides the improved fuel economy.

Design and Performance Analysis of Fuel Feed and Fuel Transfer System for Smart UAV (스마트무인기 연료이송/공급 계통의 설계 및 성능분석)

  • Lee Chang-Ho;Lee Soo-Cheol;Choi Hee-Joo;Kim Jai-Moo
    • Proceedings of the Korean Society of Propulsion Engineers Conference
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    • 2006.05a
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    • pp.351-354
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    • 2006
  • In the present work, performance analysis of fuel feed and transfer system for Smart UAV was conducted. For the fuel feed system, it was verified that minimum and maximum pressure requirements at the fuel inlet of engine were satisfied. For the fuel transfer system, design variables of jet pump were derived and performance was verified for the maximum acceleration flight condition by using ESDU design guide and flowmaster code.

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Fuel Cells for Intermediate Temperature Operations (저온 작동 박막 고체산화물 연료전지)

  • Shim, Joon-H.;Cha, Suk-Won;Gur, Turgut M.;Prinz Fritz B.
    • Journal of the Korean Ceramic Society
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    • v.43 no.12 s.295
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    • pp.751-757
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    • 2006
  • Recently, a new type of solid oxide fuel cells has been developed employing extremely thin oxide electrolyte. These fuel cells are expected to operate at significantly reduced temperature compared to conventional solid oxide fuel cells. Accordingly, they may resolve the stability and material selection issues of high temperature fuel cells. Furthermore, they may eliminate the limitations of polymer membrane fuel cells whose operation temperature is under $100^{\circ}C$. In this paper, we review the electrolytes for intermediate temperature operation. Then, we discuss the current development of thin film solid oxide fuel cells that possibly operated at low temperatures.

Stress Analysis of IPS Lower bracket

  • Lee, J.M.;Park, K.N.;Chi, D.Y.;Park, S.K.;Sim, B.S.;Lee, H.H.;Ahn, S.H.;Lee, C.Y.;Kim, H.R.
    • Proceedings of the Korean Nuclear Society Conference
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    • 2005.10a
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    • pp.703-704
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    • 2005
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Investigation on the effect of eccentricity for fuel disc irradiation tests

  • Scolaro, A.;Van Uffelen, P.;Fiorina, C.;Schubert, A.;Clifford, I.;Pautz, A.
    • Nuclear Engineering and Technology
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    • v.53 no.5
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    • pp.1602-1611
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    • 2021
  • A varying degree of eccentricity always exists in the initial configuration of a nuclear fuel rod. Its impact on traditional LWR fuel is limited as the radial gap closes relatively early during irradiation. However, the effect of misalignment is expected to be more relevant in rods with highly conductive fuels, large initial gaps and low conductivity filling gases. In this paper, we study similar characteristics in the experimental setup of two fuel disc irradiation campaigns carried out in the OECD Halden Boiling Water Reactor. Using the multi-dimensional fuel performance code OFFBEAT, we combine 2-D axisymmetric and 3-D simulations to investigate the effect of eccentricity on the fuel temperature distribution. At the same time, we illustrate how the advent of modern tools with multi-dimensional capabilities might further improve the design and interpretation of in-pile separate-effect tests and we outline the potential of such an analysis for upcoming experiments.

A Study on Thermal Performance Evaluation Procedures of LNG Fuel Tank (LNG 연료탱크의 단열성능 평가 절차에 관한 연구)

  • Cho, Sang-Hoon;Sim, Myung-Ji;Jung, Young-Jun;Kim, Ik-Soo
    • Journal of the Korean Institute of Gas
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    • v.22 no.3
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    • pp.45-52
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    • 2018
  • As guidelines for exhaust gases of ship are reinforced by the International Maritime Organization, the necessity for LNG fuelled ship is emerging. The relevant research is actively progressing to develop technologies and promote commercialization. When the residual quantity of LNG fuel tank is less than 70% by consuming fuel during operation, sloshing should be considered. We applied the Type C LNG fuel tank because medium sized LNG fuelled ships are difficult to equip with re-liquefaction system. Structural integrity and thermal performance are very important, especially in LNG fuel tanks that apply to LNG fuelled ship. Through this study, we proposed evaluation procedure of thermal performance for the Type C LNG tank, and verified the validity and effectiveness of BOR(Boil-Off Rate) test Procedure by comparing and analyzing changes in temperature, pressure, BOG(Boil-Off Gas).

Determination of carbon-14 and tritium in a PWR spent nuclear fuel (PWR 사용후핵연료 중 탄소-14 및 트리튬 정량)

  • Kim, Jung Suk;Park, Soon Dal;Lee, Chang Hun;Song, Byong Chul;Jee, Kwang Yong
    • Analytical Science and Technology
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    • v.18 no.4
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    • pp.298-308
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    • 2005
  • The methods for determining C-14 and tritium contents in the spent nuclear fuel sample were developed. The carbon-14($^{14}CO_2$) released during the dissolution of the spent fuel sample and $CaCO_3$ ($CO_2$ carrier) with 8 M $HNO_3$ at $90^{\circ}C$ was collected in trap containing 1.5 M NaOH. The volatile radioactive iodine evolved when the spent fuel was dissolved, was trapped on to Ag-silicagel (Ag-impregnated silicagel) adsorbent in column which is connected to two NaOH traps. The solutions which contain tritium as HTO after fuel dissolution were decontaminated by deionization with a mixture of cation and anion exchange resins and inorganic ionexchangers. The amount of C-14 in the trap solutions and the HTO concentration in the resulting deionization water were then determined by liquid scintillation counting.