• Title/Summary/Keyword: domestic accident

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Research on Vehicle Crash Compatibility Through Car to Car Frontal Crash Test (차 대 차 정면충돌시험을 통한 상호안전성 연구)

  • Park, In-Song;Kim, Guan-Hee;Hong, Seung-Jun
    • Transactions of the Korean Society of Automotive Engineers
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    • v.15 no.5
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    • pp.72-77
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    • 2007
  • Since 2000, sports utility vehicles(SUVs) occupy about 40% of domestic vehicle sales. As sports utility vehicle sales are increased the probability of crash accident between SUVs and passenger vehicles increases. Generally, SUVs are heavier than passenger vehicles and their drive height and front end stillness are higher than passenger vehicles. Because of these characteristics SUVs cause more severe injury and fatal injury in SUV to passenger vehicle head-on impact. To evaluate SUV's aggessivity to passenger vehicle, we carried out SUV to passenger vehicle head-on crash test. And finally the way how to reduce incompatibility between SUVs and passenger vehicles is suggested.

Review of Evaluation Method for Nuclear Power Plant Pipings under Beyond Design Basis Earthquake Condition (설계기준초과지진에 대한 원전 배관 평가 방법 검토)

  • Lee, Dae Young;Park, Heung Bae;Kim, Jin Weon;Kim, Yun-Jae
    • Transactions of the Korean Society of Pressure Vessels and Piping
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    • v.12 no.1
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    • pp.56-61
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    • 2016
  • After Japanese Fukushima nuclear power plant accident caused by the beyond design basis earthquake and tsunami, it has turned to be a major challenge for nuclear safety. IAEA, US NRC and EU have provided new safety design standards for beyond design basis event, Domestic regulatory bodies have also enacted guidances for licensees and applicants on additional methods related to beyond design basis events. This paper describes several evaluation methods for applying to nuclear power plants piping for beyond design basis earthquake. As a results, energy method based on the absorbed energy on nuclear power plant, deterministic method following design code and theory, experience method considering past earthquake data and information and probabilistic methods similar to probabilistic risk assessment were reviewed.

Development of the Railway Crossing Risk Assessment Software; Focused on the Improvement of Parametric Record Management for Railway Crossings Safety (철도건널목의 위험평가 S/W개발 ; 철도건널목 안전관리를 위한 이력관리대상 도출을 중심으로)

  • Hong Seon-Ho;Wang Jong-Bae;Kim Sang-Ahm;Park Chan-Uh
    • Proceedings of the KSR Conference
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    • 2004.06a
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    • pp.254-261
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    • 2004
  • Recently because of high-speed operation of trains, railway crossings become more and more hazardous components among the whole ones of railway system. It is desirable to remove all the railway crossings for reducing fatalities at railway crossings. it is impossible to eliminate all the crossings for unrealistic investment, so it should be considered to construct multi-level crossings by the order of priority. In this paper operation conditions, various hazard factors on the train accident at domestic railway crossings and foreign cases of risk-based safety assessment models are reviewed and then necessary record data that be added and modified, some essential considerations for developing railway crossing safety assessment software program are proposed.

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A Study on the Development of a Expert-System through a Real-Time Combination of MMIS and SIS (실시간 설비/안전정보관리시스템의 전문가시스템 구현방안에 관한 연구)

  • 박주식;임총규;오지영;강경식
    • Journal of the Korea Safety Management & Science
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    • v.3 no.3
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    • pp.1-9
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    • 2001
  • To keep an enterprise's competitiveness on the condition of the automatic manufacturing system such as FA, FMS and CIM, all the maintenance problems should be considered seriously In not only in production and maintenance but also in related industrial safety. As we analyze in the surveys the maintenance management of domestic enterprises and the causes of Industrial accident, there will be necessity of drawing up countermeasures for preventing industrial accidents and for ensuring expertise maintenance technologies. Based on these analyses, the safety information system, maintenance management information system, and the machinery condition diagnosis technique are studied by using of the knowledge-based system under the real-time computer-operating environment and using fuzzy linguistic variable. This computer system based knowledge-based diagnosis can easily provide not only the knowledge of expert system about deterioration phenomenon of industrial robots, but also the knowledge of relating safety and facility all the time. Therefore, it is expected to improve the efficiency of business processes in the production and safety when we use this system.

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A Safety Plan for the Pumping Station by Hydraulic Transient Analysis and Demonstration (과도수리현상 해석과 실증을 통한 펌프장 안정성 확보방안)

  • Ra, Beyong-pil;Kim, Jin-min;Lee, Dong-keun;Park, Jong-ho;Kim, Kyung-yup
    • The KSFM Journal of Fluid Machinery
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    • v.8 no.5 s.32
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    • pp.22-28
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    • 2005
  • As the water supply facilities are recently getting larger, the domestic waterworks become multi-regional water supply system. Large water supply facilities generally consist of the intake pumping station, water treatment plant and water supply/distribution facilities. Although the pumping stations and the pipeline systems are used to pump up water, it often happens pipeline damage and flooding accident by the water hammer. In this paper, the intake pumping station is guaranteed by both the computer simulation and the field test analysis. This study is contributed to the safe operation program for the pumping station in which results of the adjustment on the safety plan of the pumping station, the air valve and the valve closing time.

Reagent Cabinet Management System Using Danger Priority

  • Cao, Kerang;Kang, Inshik;Choi, Hyungwook;Jung, Hoekyung
    • Journal of information and communication convergence engineering
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    • v.15 no.4
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    • pp.227-231
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    • 2017
  • Recently, as the number of safety accidents caused by reagents increases, researches on a system that can reduce safety accidents are underway. Existing systems managed reagent cabinet through various sensors. On the other hand, there are disadvantages in that countermeasures against simultaneous danger situations are insufficient at multi-reagents cabinet. In order to solve this problem, this paper proposes a system to manage the reagents cabinet through danger priority. Danger priorities are selected through domestic chemical accident cases and the Chemical Safety Management Act. If a danger situation occurs in the reagent cabinet, make sure it is from a single or multiple reagent cabinets. For multiple reagent cabinets, compare the reagent cabinet priorities and run the device sequentially from the reagent cabinet with the highest priority. Thus, by operating the device according to the danger priority, the chain reaction can be prevented in advance and the reagent cabinet can be safely managed.

DEVELOPMENT OF A FRAMEWORK FOR ASSESSING RADIATION SOURCE TERMS IN NUCLEAR POWER PLANTS

  • Jae, Moo-Sung;Park, Shane;Kang, Kyung-Min;Jeun, Gyoo-Dong
    • Journal of Radiation Protection and Research
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    • v.26 no.3
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    • pp.197-201
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    • 2001
  • A risk analysis consists of a triplet, , where Si is the scenario identification; Pi is the probability of each scenario; and Xi is the consequences of each scenario. A new computing framework, OMAM (ORIGEN-MAAP4-MMCS), has been developed and applied for assessing the risk of a reference plant as well as radiation source terms using the concept of risk triplet. The result of this study using the OMAM framework presented in this paper, can contribute to producing domestic nuclear power plant's risk data base as well as to establishing severe accident management plans.

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Optimal Design for a Structure Using Design of Experiment (실험계획법을 이용한 구조물의 최적설계)

  • 고성호;한석영;최형연
    • Proceedings of the Korean Society of Machine Tool Engineers Conference
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    • 2001.04a
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    • pp.34-39
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    • 2001
  • The median barrier is one of the roadside hardware to prevent severe human and property damage from highway traffic accidents. The foreign standard of concrete median barrier was introduced and implemented without modification fitting to domestic vehicle and highway condition. In a car accident, median barrier doesn't protect vehicle effectively, especially for heavy vehicle such as bus and heavy truck. The purpose of this study is to develop the optimal performance design of concrete median barrier using the design of experiment with crash simulation analysis which is done by Pam-Crash that is one of the commercial crash simulation software. As a result of this study, an optimal design of concrete median barrier is obtained considering von Mises stress, volume and COG acceleration of truck.

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Technology development on automatic changeover system in neutral section with energized condition of electric railway catenary system (절연구간 무접점 자동 전원절체 통과시스템 기술개발)

  • Hong, Hyun-Pyo;Han, Moon-Seob;Seo, Myung-Seok;Shin, Myong-Cheol;Yoon, Yong-Han;Kim, Jae-Chul
    • Proceedings of the KSR Conference
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    • 2010.06a
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    • pp.498-506
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    • 2010
  • The neutral section was installed in order to prevent conflict with different phase angle source in electric railway catenary system. The speed of electric train reduced due to coasting operation by notch off when it passed the neutral section. And, the catenary wire was damaged and the accident might be happened because of the arc generation when the electric train passed the neutral section with notch on condition. This project has a goal to develop the automatic changeover system using by noncontactless semiconductor device in neutral section of catenary system so that the train pass as notch-on condition. In this first year, we obtain as following results such as domestic and international systems applications and completion requirements, development and analysis of stability for automatic changeover system, design of static switching device on automatic changeover system in neutral section and drawing up interface design and specifications according to equipment.

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Analysis of Failure Probabilities of Pipes in Nuclear Power Plants due to Stress Corrosion Cracking (원자력 발전소 배관의 응력부식에 의한 파손확률 해석)

  • Park, Jai-Hak;Lee, Jae-Bong;Choi, Young-Hwan
    • Journal of the Korean Society of Safety
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    • v.26 no.2
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    • pp.6-12
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    • 2011
  • The failure probabilities of pipes in nuclear power plants due to stress corrosion are obtained using the P-PIE program, which is developed for evaluating failure probability of pipes based on the existing PRAISE program. Leak, big leak and LOCA(loss of coolant accident) probabilities are calculated as a function of operating time for several pipes in a domestic nuclear plant. The sensitivity analysis is also performed to find out the important parameters for the failure of pipes due to stress corrosion. The results show that the steady state oxygen concentration and steady state temperature are important parameters and failure probability is very low when the oxygen concentration is maintained according to the regulation.