• 제목/요약/키워드: Gas Leakage

검색결과 721건 처리시간 0.021초

자동차의 블랙박스 와이어링 화재 위험성에 관한 연구 (A Study on the Fire Risk of Black Box Wiring in Motor Vehicle)

  • 강신동;김주희;최준표;김재호
    • 한국안전학회지
    • /
    • 제32권6호
    • /
    • pp.22-28
    • /
    • 2017
  • According to the National Fire Data System (NFDS), more than 5,000 vehicle fires have occurred every year for the last 10 years. Vehicle fires are primarily caused by mechanical (breaking system and engine), electrical (wiring and battery), and chemical (oil and fuel gas leakage) problems. The electrical factor has increased with the installation of driver convenience equipment. For example, today, the black box is widely used to provide video data recording of motor vehicle accidents. The black box consists of a front camera, rear camera, and wires. The black box wires are directly connected to the junction box or fuse box from the start battery that operates to provide normal on power supplying for engine stop. It is extremely dangerous when the wires short circuit due to insulation aging, mechanical and electrical stress, etc. In this study, the black box wiring fire risk have been analyzed and investigated when the steady state and abnormal operations, and under the following conditions: wiring arrangements with a high temperature condition, insulation aging, poor contact, and short circuits. The results showed that black box wiring short circuits had a higher fire risk than the other fire hazard elements. To prevent fire hazards caused by black box wiring, the black boxes must be installed by qualified service personnel. Do not modify the wiring, remove the fuse and secure the wiring using cable ties or insulation tape.

중수로 사용후연료 건전성 검사장비 개발 (Development of CANDU Spent Fuel Bundle Inspection System and Technology)

  • 김용찬;이종현;송태한
    • 방사성폐기물학회지
    • /
    • 제11권1호
    • /
    • pp.31-39
    • /
    • 2013
  • 핵연료는 원자로 운전 중 예기치 못한 상황에서 연료 결함을 초래할 수 있다. 핵연료 결함은 연료봉의 수소화나 이물질에 의한 금속 마모, 그리고 펠렛과 피복관의 상호작용에 의해 피복관이 손상된다. 이렇게 손상된 핵연료의 결함원인을 규명하는 것은 원자력발전의 안전운전에 중요하다고 사료된다. 핵연료가 손상되면 원자로 냉각재가 오염되어 원자로 출력을 낮추거나, 발전소를 정지할 수도 있다. 모든 사용후연료는 건식저장고로 이동 보관되어야 하나, 결함연료는 이동할 수 없으므로 이 연구의 목적은 중수로형 원자로에서 연료가 인출된 후 사용후연료 저장조에서 보관된 연료에 대하여 결함 여부를 판단할 수 있는 기술을 개발하고자 하였다. 이 연구를 통하여 핵종 누설 검출 기술을 이용한 사용후연료 검사기술을 개발하였으며, 이 기술을 월성발전소에 적용함으로써, 검사기술 및 검사시스템에 대한 성능을 입증하였다.

Mitigation of Ammonia Dispersion with Mesh Barrier under Various Atmospheric Stability Conditions

  • Gerdroodbary, M. Barzegar;Mokhtari, Mojtaba;Bishehsari, Shervin;Fallah, Keivan
    • Asian Journal of Atmospheric Environment
    • /
    • 제10권3호
    • /
    • pp.125-136
    • /
    • 2016
  • In this study, the effects of the mesh barrier on the free dispersion of ammonia were numerically investigated under different atmospheric conditions. This study presents the detail and flow feature of the dispersion of ammonia through the mesh barrier on various free stream conditions to decline and limit the toxic danger of the ammonia. It is assumed that the dispersion of the ammonia occurred through the leakage in the pipeline. Parametric studies were conducted on the performance of the mesh barrier by using the Reynolds-averaged Navier-Stokes equations with realizable k-${\varepsilon}$ turbulence model. Numerical simulations of ammonia dispersion in the presence of mesh barrier revealed significant results in a fully turbulent free stream condition. The results clearly show that the flow behavior was found to be a direct result of mesh size and ammonia dispersion is highly influenced by these changes in flow patterns in downstream. In fact, the flow regime becomes laminar as flow passes through mesh barrier. According to the results, the mesh barrier decreased the maximum concentration of the ammonia gas and limited the risk zone (more than 500 ppm) lower than 2 m height. Furthermore, a significant reduction occurs in the slope of the upper boundary of $NH_3$ risk zone distribution at downstream when a mesh barrier is presented. Thus, this device highly restricts the leak distribution of ammonia in the industrial plan.

이산화탄소 해양 지중저장 시스템에서의 누출 위해성 평가방법에 관한 기술적 검토 (Technical Review on Risk Assessment Methodology for Carbon Marine Geological Storage Systems)

  • 황진환;강성길;박영규
    • 한국해양환경ㆍ에너지학회지
    • /
    • 제13권2호
    • /
    • pp.121-125
    • /
    • 2010
  • 지중 저장기술은 대기로 방출되는 이산화탄소를 저감하는 기술로서 기후변화를 발생하는 온실효과를 저감 시킬 수 있다. 해양 저지대에 위치한 심층 대수층 혹은 폐유전 등은 이러한 이산화탄소 저장기술의 중요한 후보군이라고 할 수 있다. 관련된 이산화탄소 주입 및 저장기술은 전 세계적으로도 많은 관심을 받고 있으나, 이러한 시스템에서 이산화탄소 누출이 발생하였을 때의 부정적 영향에 대해서는 아직 심도 있는 연구는 진행되지 못하고 있다. 이산화탄소 저장기술의 안정성이 매우 높아서 누출의 가능성은 매우 낮다고 하더라도, 고농도의 이산화탄소가 만약의 사태에서 누출이 된다면 여전히 해양생태계 및 환경에 위험이 있을 수 있다. 그러나 이에 대한 연구가 충분히 이루어지지 않았기에, 본 연구에서는 하나의 신뢰성 및 위해성 평가방법을 소개하고자 한다. Feature, Event and Process(FEP)를 통해 다양한 요소를 고려하고, 결함수 분석을 통해 신뢰도를 평가하는 방법을 제안한다. 이러한 FEP 분석으로 시스템에서 시공 및 운영과정에서 발생할 수 있는 다양한 누출 가능성을 평가하는 방법을 소개하였다.

IEC 기술표준의 가스폭발위험범위 연구 (A Study on Gas Explosion Hazardous Ranges for International Electrotechnical Commission Technical Standards)

  • 정용재;이창준
    • 한국안전학회지
    • /
    • 제33권3호
    • /
    • pp.39-45
    • /
    • 2018
  • The occupational safety and health act defines how to evaluate the explosion hazardous areas according to KS (Korean Industrial Standards). Current KS have to follow IEC (International Electrotechnical Commission) 60079-10-1 1st edition and there has been no change since 2008. And its 2nd edition has been revised in 2015. In this study, IEC 1st Ed. (IEC 60079-10-1 1st edition) is compared with IEC 2nd edition. Total 112 case studies including four materials (methane, propane, benzene, methanol) are selected to test and explosion hazardous ranges evaluated by IEC 1st and 2nd Ed. are analyzed according to various leakage pressures and hole sizes. In order to verify the results calculated by them, PHAST, which is one of the most representative consequence analysis programs, is employed. As a result, it can be concluded that there are many differences between IEC 1st and 2nd Ed. due to the discharge and the ventilation parameters. As comparing with PHAST, it is confirmed that IEC 1st provides more conservative values than PHAST. Even if IEC 2nd Ed. provides more conservative for gases, this fails to provide more conservative values for liquids. Therefore, it is worth to note that a large value between the explosion hazardous ranges value calculated by the IEC 1st Ed. and 2nd Ed. should be selected until further investigation and analysis is made. Morevover, the full consideration for IEC 2nd Ed. have to be needed.

(Pb0.72La0.28)Ti0.94O3 Buffer를 사용한 Pb(Zr0.52Ti0.48)O3 박막의 수소 후열처리 효과 (Effect of the Hydrogen Annealing on the Pb(Zr0.52Ti0.48)O3 Film using (Pb0.72La0.28)Ti0.94O3 Buffers)

  • 이은선;이동화;정현우;임성훈;이상렬
    • 한국전기전자재료학회논문지
    • /
    • 제18권4호
    • /
    • pp.327-329
    • /
    • 2005
  • Pb(Zr/sub 0.52/Ti/sub 0.48/)O₃(PZT) thin films were deposited by using a pulsed laser deposition method on a Pt/Ti/SiO₂/Si substrate with (Pb/sub 0.72/La/sub 0.28/)Ti/sub 0.93/O₃ (PLT) buffer and on a Pt/Ti/SiO₂/Si substrate without buffer. These films were annealed in H₂-contained ambient for 30 minutes at the substrate temperature of 400。C to evaluate the forming gas annealing effects. The comparative studies on the ferroelectric properties of these two films were carried out, which are shown that ferroelectric properties, such as remanent polarization didn't change in the case of PLT buffered PZT film while remanent polarization value of PZT film degraded from 20.8 C/㎠ to 7.3 C/㎠. The leakage current became higher in both cases, but that of the more-oriented PZT film had the moderate value of the 10/sup -6/ order of A/㎠. This is mainly because the hydrogen atoms which make the degradation of PZT films cannot infiltrate into the more -oriented PZT film as well as the less-oriented PZT film.

해외원전 비계획적 방출 및 한국의 환경감시 현황 분석 (Review of Unplanned Release at Foreign Nuclear Power Plants and Radiological Monitoring at Korean Power Plants)

  • 박수찬;함박눈;권장순;조동건;정지혜;권만재
    • 한국지하수토양환경학회지:지하수토양환경
    • /
    • 제23권4호
    • /
    • pp.1-15
    • /
    • 2018
  • Despite of safety issues related to radiological hazards, 31 countries around the world are operating more than 450 nuclear power plants (NPPs). To operate NPPs safely, safety regulations from radiation protection organizations were developed and adopted in many countries. However, many cases of radionuclide releases at foreign NPPs have been reported. Almost all commercial NPPs routinely release radioactive materials to the surrounding environments as liquid and gas phases under control. These releases are called 'planned releases' which are planned, regularly monitored, and well documented. Meanwhile, the releases focused in this review, called 'unplanned releases', are neither planned nor monitored by regulatory and/or protection organizations. NPPs are generally composed of various structures, systems and components (SSCs) for safety. Among them, the SSCs near reactors are closely related to safety of NPPs, and typically fabricated to comply with stringent requirements. However, some non-safety related SSCs such as underground pipes may be constructed only according to commercial standards, causing the leakage of radioactive fluids usually containing tritium ($^3H$). This paper discusses SSCs of NPPs and introduces several cases of unplanned releases at foreign NPPs. The current regulation on the environmental radiological surveillance and assessment around the NPPs in South Korea are also examined.

Adverse Effects on Crops and Soils Following an Accidental Release of Hydrogen Fluoride and Hydrofluoric Acid

  • Kang, Dae-Won;Kim, Hyuck-Soo;Kunhikrishnan, Anitha;Kim, Da-In;Lee, Seul;Park, Sang-Won;Yoo, Ji-Hyock;Kim, Won-Il
    • 한국토양비료학회지
    • /
    • 제49권6호
    • /
    • pp.651-654
    • /
    • 2016
  • A number of accidents relating to highly toxic hydrogen fluoride (HF) or hydrofluoric acid (HA) release have occurred over fast few decades in Korea. Thus, this study was conducted to investigate the fluoride (F) concentrations in paddy soil and brown rice from 2 different areas where the soils were exposed to HF and HA. In the first case, the HF leakage accident that occurred in 2012 affected the surrounding soils and crops and consequently, crops (rice) affected by HF were unavailable for forage even though F did not accumulate in the soil. For example, at the time of accident, F concentrations in brown rice samples were $33.0-1,395mg\;kg^{-1}$, while F concentrations in soil samples were $155-295mg\;kg^{-1}$ which were less than the Korean standard guideline values of $400mg\;kg^{-1}$. However, after a year, F concentrations in brown rice were observed below the detection limit ($1mg\;kg^{-1}$), although F concentrations in soils were similar with those in 2012. Also, large amounts of wastewater discharges containing HA occurred in 2013 and some agricultural soils exceeded the Korean standard guideline values for F ($400mg\;kg^{-1}$), but soil-plant F transfer was not observed. In conclusion, it was observed that soil to plant transfer of F is unlikely although HF and HA as gas or liquid form can cause direct damage to plants.

Nonstoichiometric Effects in the Leakage Current and Electrical Properties of Bismuth Ferrite Ceramics

  • Woo, Jeong Wook;Baek, SeungBong;Song, Tae Kwon;Lee, Myang Hwan;Rahman, Jamil Ur;Kim, Won-Jeong;Sung, Yeon Soo;Kim, Myong-Ho;Lee, Soonil
    • 한국세라믹학회지
    • /
    • 제54권4호
    • /
    • pp.323-330
    • /
    • 2017
  • To understand the defect chemistry of multiferroic $BiFeO_3-based$ systems, we synthesized nonstoichiometric $Bi_{1+x}FeO_{3{\pm}{\delta}}$ ceramics by conventional solid-state reaction method and studied their structural, dielectric and high-temperature charge transport properties. Incorporation of an excess amount of $Bi_2O_3$ lowered the Bi deficiency in $BiFeO_3$. Polarization versus electric field (P-E) hysteresis loop and dielectric properties were found to be improved by the $Bi_2O_3$ addition. To better understand the defect effects on the multiferroic properties, the high temperature equilibrium electrical conductivity was measured under various oxygen partial pressures ($pO_2{^{\prime}}s$). The charge transport behavior was also examined through thermopower measurement. It was found that the oxygen vacancies contribute to high ionic conduction, showing $pO_2$ independency, and the electronic carrier is electron (n-type) in air and Ar gas atmospheres.

I-V and C-V measurements or fabricated P+/N junction mode in Antimony doped (111) Silicon

  • Jung, Won-Chae
    • Transactions on Electrical and Electronic Materials
    • /
    • 제3권2호
    • /
    • pp.10-15
    • /
    • 2002
  • In this paper, the electrical characteristics of fabricated p+-n junction diode are demonstrated and interpreted with different theoretical calculations. Dopants distribution by boron ion implantation on silicon wafer were simulated with TRIM-code and ICECaEM simulator. In order to make electrical activation of implanted carriers, thermal annealing treatments are carried out by RTP method for 1min. at $1000^{circ}C$ under inert $N_2$ gas condition. In this case, profiles of dopants distribution before and after heat treatments in the substrate are observed from computer simulations. In the I-V characteristics of fabricated diodes, an analytical description method of a new triangular junction model is demonstrated and the results with calculated triangular junction are compared with measured data and theoretical calculated results of abrupt junction. Forward voltage drop with new triangular junction model is lower than the case of abrupt junction model. In the C-V characteristics of diode, the calculated data are compared with the measured data. Another I-V characteristics of diodes are measured after proton implantation in electrical isolation method instead of conventional etching method. From the measured data, the turn-on characteristics after proton implantation is more improved than before proton implantation. Also the C-V characteristics of diode are compared with the measured data before proton implantation. From the results of measured data, reasonable deviations are showed. But the C-V characteristics of diode after proton implantation are deviated greatly from the calculated data because of leakage currents in defect regions and layer shift of depletion by proton implantation.