• 제목/요약/키워드: Liquid fuel pool

검색결과 29건 처리시간 0.018초

주 변압기실 화재시나리오에 적용한 미세물분무 노즐의 소화성능 (Performance of Fire Extinguishing of Water Mist Nozzle for Power Transformer Fire Scenario)

  • 이경덕
    • 한국안전학회지
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    • 제21권6호
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    • pp.46-54
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    • 2006
  • Fire extinguishing experiment was conducted with water mist nozzle in case of the pool fire, cascade fire and spray fire on flammable liquid of class B whether water mist system can be effective system for power transformer fire scenario. In the event of a pool fire, flow rate and time to extinguish was inclined to be increased according to the obstruction rate of ignition space. Furthermore, the performance of fire extinguishing depended upon the spraying angle of the nozzles. In case of cascade fire, the effect of extinguishment was began to show from a combustion pan filled with fuel and fuel flowing plate later on.

화점높이 변화에 따른 메탄올의 소규모 Pool 및 Whirl Fire의 연소특성 (Combustion Characteristics of Pool and Whirl Fire on Methanol by Height of Fire Source using the Small Scale)

  • 박형주
    • 한국화재소방학회논문지
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    • 제26권3호
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    • pp.73-78
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    • 2012
  • 화점높이 변화에 따른 풀 화재와 회오리 화염의 연소특성을 알아보기 위하여 인화성 액체인 메탄올을 $100{\times}100{\times}50$ 크기의 스테인레스 재질의 사각형 용기에 넣고 연소실험을 하였다. 연소시간, 질량감소속도, 화염온도, 화염높이 및 외부로부터 화염으로의 공기유입속도 등을 측정하였으며, 연소시 화염의 거동은 비디오카메라를 이용하였다. 모든 실험결과로부터 화점높이 변화에 따른 연소특성은 풀 화재보다는 회오리 화염에 있어서 더 큰 영향을 준다는 것을 알 수 있었다.

나트륨 염이 첨가된 미분무수의 액체 pool fire소화특성 (Extinguishing Characteristics of Liquid Pool Eire by Water Mist Containing Sodium Salt)

  • 박재만;신창섭
    • 한국화재소방학회논문지
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    • 제19권3호
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    • pp.13-19
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    • 2005
  • 본 논문에서는 금속염 첨가제를 함유한 미분무수의 소화성능을 연구하고자 아세트산 나트륨을 함유한 단일 액적의 증발속도를 측정하였으며, small-scale 챔버내에서의 헵탄 pool fire에 대한 소화실험을 실시하여, 화염의 온도를 분석함으로써 첨가제에 의한 미분무수 소화특성을 분석하였다. 순수물과 수용액의 증발특성을 비교한 결과 핵비등 영역에서 온도가 높을수록 용해된 첨가제의 석출 및 표면장력의 변화 등 물리적 영향으로 순수물에 비해 수용액의 증발속도가 현저히 느리게 나타났다. 소화실험 결과, 저압에서는 물 액적이 화염의 플림을 뚫지 못하기 때문에 소화는 이루어지지 않았고 단순히 화염의 크기를 작아지게 하였다. 중압에서는 첨가제를 넣었을 경우 액적의 운동량 증가에 따른 물리적 소화효과와 첨가제의 화학적 소화효과가 상승작용을 하여 화염을 억제하였고, 고압에서는 미분무수 시스템의 주요 소화 메커니즘 이외에도 blowing효과에 의해서 화염이 소화되는 것을 관찰할 수 있었다.

다차원 노심열수력 현상이 소듐고속로 고유안전성에 미치는 영향 (Impact of Multi-dimensional Core Thermal-hydraulics on Inherent Safety of Sodium-Cooled Fast Reactor)

  • 권영민;정해용;하귀석
    • 대한기계학회:학술대회논문집
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    • 대한기계학회 2008년도 추계학술대회B
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    • pp.3175-3180
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    • 2008
  • A metal-fueled pool-type liquid metal fast reactor (LMFR) provides large margins to sodium boiling and fuel damage under accident conditions. The favorable passive safety results are obtained by both a reactivity feedback mechanism in the core and a passive decay heat removal system. Among the various reactivity feedbacks, the ones by a thermal expansion of a radial dimension of the core and by the control rod drivelines are strongly dependent on the flow conditions in the core and the hot pool, respectively. The effects of multidimensional thermal hydraulic characteristics on these reactivity feedbacks are investigated by the system-wide safety analysis code SSC-K with advanced thermal hydraulics models. Particularly a detailed three dimensional thermal hydraulics reactor core model is integrated into SSC-K for use in a whole system analysis of the passive safety aspects of LMR designs. The model provides fuel and cladding temperatures for every fuel pin in a reactor and coolant temperatures for every coolant sub-channel in the reactor.

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Conceptual Safety Design Analyses of Korea Advanced Liquid Metal Reactor

  • Suk, S.D.;Park, C.K.
    • Nuclear Engineering and Technology
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    • 제31권6호
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    • pp.66-82
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    • 1999
  • The national long-term R&D program, updated in 1997, requires Korea Atomic Energy Research Institute(KAERI) to complete by the year 2006 the basic design of Korea Advanced Liquid Metal Reactor(KALIMER), along with supporting R&D work, with the capability of resolving the issue of spent fuel storage as well as with significantly enhanced safety. KALIMER is a 150 MWe pool-type sodium cooled prototype reactor that uses metallic fuel. The conceptual design is currently under way to establish a self-consistent design meeting a set of major safety design requirements for accident prevention. Some of the current emphasis includes those for inherent and passive means of negative reactivity insertion and decay heat removal, high shutdown reliability, prevention of and protection from sodium chemical reaction, and high seismic margin, among others. All of these requirements affect the reactor design significantly and involve extensive supporting R&D programs. This paper summarizes some of the results of conceptual engineering and design analyses performed for the safety of HAMMER in the area of inherent safety, passive decay heat removal, sodium water reaction, and seismic isolation.

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Knowledge from recent investigations on sloshing motion in a liquid pool with solid particles for severe accident analyses of sodium-cooled fast reactor

  • Xu, Ruicong;Cheng, Songbai;Li, Shuo;Cheng, Hui
    • Nuclear Engineering and Technology
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    • 제54권2호
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    • pp.589-600
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    • 2022
  • Investigations on the molten-pool sloshing behavior are of essential value for improving nuclear safety evaluation of Core Disruptive Accidents (CDA) that would be possibly encountered for Sodium-cooled Fast Reactors (SFR). This paper is aimed at synthesizing the knowledge from our recent studies on molten-pool sloshing behavior with solid particles conducted at the Sun Yat-sen University. To better visualize and clarify the mechanism and characteristics of sloshing induced by local Fuel-Coolant Interaction (FCI), experiments were performed with various parameters by injecting nitrogen gas into a 2-dimensional liquid pool with accumulated solid particles. It was confirmed that under different particle-bed conditions, three representative flow regimes (i.e. the bubble-impulsion dominant, transitional and bed-inertia dominant regimes) are identifiable. Aimed at predicting the regime transitions during sloshing process, a predictive empirical model along with a regime map was proposed on the basis of experiments using single-sized spherical solid particles, and then was extended for covering more complex particle conditions (e.g. non-spherical, mixed-sized and mixed-density spherical particle conditions). To obtain more comprehensive understandings and verify the applicability and reliability of the predictive model under more realistic conditions (e.g. large-scale 3-dimensional condition), further experimental and modeling studies are also being prepared under other more complicated actual conditions.

A REVIEW OF INHERENT SAFETY CHARACTERISTICS OF METAL ALLOY SODIUM-COOLED FAST REACTOR FUEL AGAINST POSTULATED ACCIDENTS

  • SOFU, TANJU
    • Nuclear Engineering and Technology
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    • 제47권3호
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    • pp.227-239
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    • 2015
  • The thermal, mechanical, and neutronic performance of the metal alloy fast reactor fuel design complements the safety advantages of the liquid metal cooling and the pool-type primary system. Together, these features provide large safety margins in both normal operating modes and for a wide range of postulated accidents. In particular, they maximize the measures of safety associated with inherent reactor response to unprotected, doublefault accidents, and to minimize risk to the public and plant investment. High thermal conductivity and high gap conductance play the most significant role in safety advantages of the metallic fuel, resulting in a flatter radial temperature profile within the pin and much lower normal operation and transient temperatures in comparison to oxide fuel. Despite the big difference in melting point, both oxide and metal fuels have a relatively similar margin to melting during postulated accidents. When the metal fuel cladding fails, it typically occurs below the coolant boiling point and the damaged fuel pins remain coolable. Metal fuel is compatible with sodium coolant, eliminating the potential of energetic fuel-coolant reactions and flow blockages. All these, and the low retained heat leading to a longer grace period for operator action, are significant contributing factors to the inherently benign response of metallic fuel to postulated accidents. This paper summarizes the past analytical and experimental results obtained in past sodium-cooled fast reactor safety programs in the United States, and presents an overview of fuel safety performance as observed in laboratory and in-pile tests.

차량화재 안전설계를 위한 휘발유/에탄올 혼합연료의 연소생성물 배출 특성 (Emission Characteristics of Gasoline/ethanol Mixed Fuels for Vehicle Fire Safety Design)

  • 김신우;이의주
    • 한국안전학회지
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    • 제34권1호
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    • pp.27-33
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    • 2019
  • Combustion characteristics of gasoline/ethanol fuel were investigated both numerically and experimentally for vehicle fire safety. The numerical simulation was performed on the well-stirred reactor (WSR) to simulate the homogeneous gasoline engine and to clarify the effect of ethanol addition in the gasoline fuel. The simulating cases with three independent variables, i.e. ethanol mole fraction, equivalence ratio and residence time, were designed to predict and optimized systematically based on the response surface method (RSM). The results of stoichiometric gasoline surrogate show that the auto-ignition temperature increases but NOx yields decrease with increasing ethanol mole fraction. This implies that the bioethanol added gasoline is an eco-friendly fuel on engine running condition. However, unburned hydrocarbon is increased dramatically with increasing ethanol content, which results from the incomplete combustion and hence need to adjust combustion itself rather than an after-treatment system. For more tangible understanding of gasoline/ethanol fuel on pollutant emissions, experimental measurements of combustion products were performed in gasoline/ethanol pool fires in the cup burner. The results show that soot yield by gravimetric sampling was decreased dramatically as ethanol was added, but NOx emission was almost comparable regardless of ethanol mole fraction. For soot morphology by TEM sampling, the incipient soot such as a liquid like PAHs was observed clearly on the soot of higher ethanol containing gasoline, and the soot might be matured under the undiluted gasoline fuel.

Extinguishment of Liquid Fuel Fire by Water Mist Containing Additives

  • Park, Jae-Man;Won, Jung-Il;Shin, Chang-Sub
    • International Journal of Safety
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    • 제4권2호
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    • pp.24-29
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    • 2005
  • An experimental study was presented for extinguishing characteristics of liquid fuel fire by water mist($Dv_{0.99}{\leq}200{\mu}m$) containing potassium acetate and sodium acetate trihydrate. To evaluate the extinguishing performance of water mist containing additives, the evaporation characteristics of a water droplet on a heated surface was examined. The evaporation process was recorded by a charge-coupled-device camera. Also, small-scale extinguishing tests were conducted for n-heptane pool fire in ventilated space. During the experiments, flame temperatures were measured, and concentrations of oxygen and carbon monoxide were analyzed by a combustion gas analyzer. The average evaporation rate of water droplet containing additives was lower than that of pure water at a given surface temperature and decreased with the concentration increase due to the precipitation of salt in the liquid-film and change of surface tension. In case of using additives, the fire extinguishing times was shorter than that of pure water at a given discharge pressure and it was because the momentum of a water droplet containing additives was increased. And also dissociated metal atoms, potassium or sodium, were reacted as a scavenger of the major radical species OH, H which were generated for combustion process. Moreover, at a high pressure of 4 MPa, the fire was extinguished through blowing effect as well as primary extinguishing mechanisms.

Dynamic Behavior of Oxide and Nitride LMR Cores during Unprotected Transients

  • Na, Byung-Chan;Dohee Hahn
    • 한국원자력학회:학술대회논문집
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    • 한국원자력학회 1997년도 춘계학술발표회논문집(1)
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    • pp.489-494
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    • 1997
  • A comparative transient analyses were performed for oxide and nitride cores or a large (3000 MWt), pool-type, liquid-metal-cooled reactor (LMR). The study was focused on three representative accident initiators with failure to scram : the unprotected loss-of-flow (ULOF), the unprotected transient overpower (UTOP), and the unprotected fast transient overpower (UFTOP). The margins to fuel melting and sodium boiling have been evaluated for these representative transients. The results show that there is an increase in safety margin with nitride core which maintains the physical dimensions of the oxide core.

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