• Title/Summary/Keyword: Protection facility

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The investigation of field condition on flood protection of substation and underground power equipment (pad-mounted transformers & switches) (수변전실 및 지중 배전기기의 침수 방지 관련 현장 조사 분석)

  • Kim, Gi-Hyun;Choi, Myeong-Il;Bae, Suk-Myong;Lee, Jae-Yong
    • Proceedings of the Korean Institute of IIIuminating and Electrical Installation Engineers Conference
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    • 2007.11a
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    • pp.327-331
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    • 2007
  • Inundation of substation and underground power equipment(pad-mounted transformers & switches) breaks out every summer season in low-lying downtown and low-lying shore by localized heavy rain, typhoon and tidal wave. In case inundation of substation and underground power equipment, it occurs a great economic loss owing to recovery time and events of electric shock occur by inundation electrical facility. So we search the damage situation and installation situations. Therefore we propose the necessity of protection of flood at low-lying downtown and low-tying shore. This paper will be used to present a reform proposal of electrical related law about flood protection of existing power equipment.

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Radiological Dose Assessment Due to the Operation of Nuclear Facilities at KAERI Nuclear Site

  • Han, M.H.;Kim, E.H.;Hwang, W.T;Yeom, J.M.;Han, J.T.;Lee, Y.B.;Han, W.J.
    • Journal of Radiation Protection and Research
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    • v.28 no.3
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    • pp.247-254
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    • 2003
  • To prevent the potential health detriment to the public from radioactive effluents, radiological dose assessments due to the operation of nuclear facilities located at Korea Atomic Energy Research Institute (KAERI) site has been performed semiannually in compliance with the Minister of Science and Technology (MOST)'s Notice in Korea. Radiological dose assessment based on the new recommendation of the International Committee on Radiation Protection (ICRP-60) has been conducted since 1998. In this manuscript, a serial activities at KAERI site to meet the regulatory standards for routine releases of radioactive effluents are introduced and discussed including technical approaches. It is clear that each nuclear facility has been operated in compliance with regulatory standards. Furthermore, it is identified that the radiation induced health effects for residents around the site are neglectable.

Conceptional Framework of Level of Protection for Facilities (시설물 방호등급 개념 설계)

  • Kee, Jung Hun;Lee, Hyun Seok;Jamot, Dongfack Guepi Clovis;Park, Jong Yil
    • Journal of the Korean Society of Safety
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    • v.30 no.3
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    • pp.67-72
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    • 2015
  • Although attention to terrorism has increased sharply in recent years within many countries, it is by no means a new phenomenon. Majority of these countries have limited regulations or guidelines about terrorism. LOP (Level Of Protection) can be consider as a first step. This paper seeks to present a process to determine LOP and allowable damage. LOP is determined by asset value reason why it should be based on cost. The asset value is defined as "cost induced when asset is damaged". For example, the collateral damage outside the facility should be taken in consideration in the asset value. Allowable structural damage is assigned depending on LOP.

An Exploratory Study on 3D-based Building Information Management for Multi-User Fire Protection System

  • Kim, Dahee;Cha, Heesung
    • International conference on construction engineering and project management
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    • 2022.06a
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    • pp.1162-1169
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    • 2022
  • As buildings become more and more complicated, the importance of developing and managing facility management information is increasing. In a building fire situation, various information is generated and needed to be quickly shared among participants. However, the current fire response system fails to monitor the relevant information in a real time basis. This study aims to develop a system prototype for fire protection management which can quickly and accurately manage and effectively deliver the pertinent information to the target participants. The research contributes to the efficiency of fire protection endeavors by interpreting both dynamic and static fire information in an appropriate manner.

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A study on Protection Coordination Method for Electric Vehicle Charging Facility based on the Wireless Power Transmission (무선전력전송 전기충전설비용 전원공급장치의 최적운용방안에 관한 연구)

  • Ryu, Kyung-Sang;Kim, Byungki;Kim, Dae-Jin;Jang, Moon-Seok;Rho, Daeseok;Ko, Hee-Sang
    • Journal of the Korea Academia-Industrial cooperation Society
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    • v.18 no.9
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    • pp.42-51
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    • 2017
  • This paper deals with the power supply facility providing wireless power transmission for a type of electric vehicles called the on-line electric vehicle(OLEV) and proposes optimal protection coordination methods which analyze the faultsin the 60Hz and 20kHz bands using PSCAD/EMTDC, which is the typical commercial software for the distribution system. The simulation results show that the proposed methods can reduce the fault current by introducing an NGR (Neutral Ground Resistor) in the 60Hz band and prevent the malfunctioning of the protection device by installing a CT in the neutral wire in the 20kHz band when a ground fault occurs.

Operation modes and Protection of VS(Vertical Stabilization) Converter for International Thermonuclear Experimental Reactor (국제 핵융합실험로용 VS(Vertical Stabilization) 컨버터의 운전모드 및 보호동작)

  • Jo, Hyunsik;Jo, Jongmin;Oh, Jong-Seok;Suh, Jae-Hak;Cha, Hanju
    • The Transactions of the Korean Institute of Power Electronics
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    • v.20 no.2
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    • pp.130-136
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    • 2015
  • This study describes the structure and operation modes of vertical stabilization (VS) converter for international thermonuclear experimental reactor (ITER) and proposes a protection method. ITER VS converter supplies voltage (${\pm}1000V$)/current (${\pm}22.5kA$) to superconducting magnets for plasma current vertical stabilization. A four-quadrant operation must be achieved without zero-current discontinuous section. The operation mode of the VS converter is separated in 12-pulse mode, 6-pulse mode and circulation current mode according to the magnitude of the load current. Protection measures, such as bypass and discharge, are proposed for abnormal conditions, such as over current, over voltage, short circuit, and voltage sag. VS converter output voltage is controlled to satisfy voltage response time within 20 msec. Bypass operation is completed within 60 msec and discharge operation is performed successfully. The feasibility of the proposed control algorithm and protection measure is verified by assembling a real controller and implementing a power system including the VS converter in RTDS for a hardware-in-loop (HIL) facility.

Comparison Study of Experimental Neutron Room Scattering Corrections with Theoretical Corrections in RCL's Calibration Facility at KAERI (한국원자력연구소 중성자교정실에 대한 중성자산란보정인자 결정연구)

  • Yoon, Suk-Chul;Chang, Si-Young;Kim, Jong-Soo;Kim, Jang-Lyul;Kim, Bong-Hwan
    • Journal of Radiation Protection and Research
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    • v.22 no.1
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    • pp.29-33
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    • 1997
  • Neutron room scattering corrections that should be made when neutron detectors are calibrated with a $D_2O$ moderated $^{252}Cf$ neutron source in the center of a calibration room are considered. Such room scattering corrections are dependent on specific neutron source type, detector type, calibration distance, and calibration room configuration. Room scattering corrections for the responses of a thermoluminescence dosimeter and two different types of spherical detectors to neutron source in the Radiation Calibration Laboratory(RCL) neutron calibration facility at the Korea Atomic Energy Research Institute(KAERI) were experimentally determined and are presented. The measured room scattering results are then compared with theoretical results calculated by predicting room scattering effects in terms of parameters related to the specific configuration. Agreement between measured and calculated scattering correction is generally about 10% for three kinds of detectors in the calibration facility.

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Preliminary Assessment of Radiation Impact from Dry Storage Facilities for PWR Spent Fuel (경수로 사용후핵연료 건식 중간저장시설에 대한 예비 방사선 영향 평가)

  • Kim, T.M.;Baeg, C.Y.;Cha, G.Y.;Lee, W.G.;Kim, S.Y.
    • Journal of Radiation Protection and Research
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    • v.37 no.4
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    • pp.197-201
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    • 2012
  • Annual dose at the boundary of the interim storage facility at normal condition was calculated to estimate the site area of the facility of PWR spent nuclear fuel. In this work, source term was generated by ORIGEN-ARP for 4.5 wt% initial enrichment, 45,000 MWd/MTU burnup and 10 years cooling time. Modeling of the storage facilities and radiation shielding evaluations were conducted by MCNP code depending on the storage capacity. In the case of the centralized storage system, the required site area was found to have the radius of more than 700 m.

Safety Assessment for LILW Near-Surface Disposal Facility Using the IAEA Reference Model and MASCOT Program (IAEA의 기준모델과 MASCOT 프로그램을 이용한 중저준위방사성폐기물 천층처분시설 안전성평가)

  • Kim, Hyun-Joo;Park, Joo-Wan;Kim, Chang-Lak
    • Journal of Radiation Protection and Research
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    • v.27 no.2
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    • pp.111-120
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    • 2002
  • A reference scenario of vault safety case prepared by the IAEA for the near-surface disposal facility of low-and informed]ate-level radioactive wastes is assessed with the MASCOT program. The appropriate conceptual models for the MASCOT implementation is developed. An assessment of groundwater pathway through a drinking well as a geosphere-biosphere interface is performed first. then biosphere pathway is analysed to estimate the radiological consequences of the disposed radionuclides based on compartment modeling approach. The validity of conceptual modeling for the reference scenario is investigated where possible comparing to the results generated by the other assessment. The result of this study shows that the typical conceptual model for groundwater pathway represented by the compartment model ran be satisfactorily used for safety assessment of the entire disposal system in a cons]stent way. It is also shown that safety assessment of a disposal facility considering complex and various pathways would be possible by the MASCOT program.