• 제목/요약/키워드: Safe-life design

검색결과 204건 처리시간 0.025초

컴퓨터시뮬레이션에 의한 피난행태예측 및 안전성능평가 방법에 관한 연구(I) (A Study on the Evaluation Method of the Building Safety Performance and the during Building Fires with Computer Prediction of Occupants′ Egress Behavior Simulation)

  • 최원령;이경회
    • 한국화재소방학회논문지
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    • 제3권1호
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    • pp.19-28
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    • 1989
  • It has been recognized that the escape facility planning is very important for effective evacuation of accupants on fire event. The ultimate goal of the escape facility planning is to evacuate occupants rapidly from building fires to the safe areas. In fire event, occupants usually gather, utilize and finally act upon information about state transient of building fire system, which is consisted of components of fire, building and accupant during the ralatively short period of the fire event. That is, occupants' egress behavior is largely dependent upon building fire system. Therefore, comprehensive study for the relationship between building fire system and occupants' egress behavior is needed. This study aims to suggest the pre -occupancy evaluation method of the life safety performance for the architectural design based on prediction of occupants' egress behavior during building fires with computer simulation.

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Development of RCM Framework for Implementation on Safety Systems of Nuclear Power Plant

  • Kim, Tae-Woon;Brijendra Singh;Park, Chang K.;Chang, Tae-Whee;Song, Jin-Bae
    • 한국원자력학회:학술대회논문집
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    • 한국원자력학회 1996년도 춘계학술발표회논문집(2)
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    • pp.631-636
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    • 1996
  • This paper presents a Reliability Centered Maintenance (RCM) framework for implementation on safety system of nuclear power plant (NPP). RCM is a systematic methodology to optimize the surveillance and maintenance tasks for critical components which provides efficiently and effectively reliability of system and safety of plant. Maintenance of the safety systems is essential for its safe and reliable operation. Reliability Centered Maintenance at NPP is the program which assure that plant system remains within original design criteria and that is not adversely affected during the plant life time. Aim of this paper is to provide the RCM framework to implement it on safety systems. RCM framework is described in four major steps.

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초고층 주상복합 아파트 단위평면의 공간구성에 관한 조사연구 (A Study on Spatial Composition of the Reusing Unit in High-rise Mixed-Use Condominium)

  • 소윤경;하미경
    • 한국주거학회논문집
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    • 제13권3호
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    • pp.45-53
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    • 2002
  • The purpose of this study is to examine the characteristics of unit plans in the high-rise mixed-use condominium and to provide the data fur architectural planning and design. The tools of statistical analysis are frequency, percentage, mean, cross-tab, and correlation. The results of this study are as fellows; The most frequently found shape of unit is a deformed polygon. The common rooms in housing units are dressing room, powder room, offset-kitchen, family room, passage, hallway, and foyer. The specially prepared spaces are wash room, home bar, independent porch, and garden. As to room size and area ratio in a dwelling unit, those of living room are biggest and highest irrespective of unit size. As the floor area of unit increases, does the size of each room and space but the area ratio of each room decreases. This research is made to develop an Apartment Information System. This integrated information system is to be designed to provide residents of high-rise mixed-use condominiums with convenient, economical, and safe life.

공기구동밸브의 열노화에 따른 성능평가 (Performance Analysis of Air Operated Valve by Thermal Aging)

  • 이선기
    • 동력기계공학회지
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    • 제19권5호
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    • pp.93-98
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    • 2015
  • Nuclear power plants has a number of valves, which are operating at a high temperature-high pressure and radiation environment conditions. Nevertheless, it is important to maintain the reliability of the valves to ensure safe operation of the nuclear power plant. However, the aging of the valves by increasing of years of plant operation and the system transients due to the sudden load change are working the failures of the reliability of the valve. In this paper, we evaluate experimentally the performance change according to the thermal aging of the valve. Results show that the valve stem and the actuator leakages were enlarged by the thermal aging.

인간과의 안전한 상호 작용을 고려한 휴머노이드 조인트 모듈 개발 (Development of Humanoid Joint Module for Safe Human-Robot Interaction)

  • 오연택
    • 로봇학회논문지
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    • 제9권4호
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    • pp.264-271
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    • 2014
  • In this study, we have developed the humanoid joint modules which provide a variety of service while living with people in the future home life. The most important requirement is ensuring the safety for humans of the robot system for collaboration with people and providing physical service in dynamic changing environment. Therefore we should construct the mechanism and control system that each joint of the robot should response sensitively and rapidly to fulfill that. In this study, we have analyzed the characteristic of the joint which based on the target constituting the humanoid motion, developed the optimal actuator system which can be controlled based on each joint characteristic, and developed the control system which can control an multi-joint system at a high speed. In particular, in the design of the joint, we have defined back-drivability at the safety perspective and developed an actuator unit to maximize. Therefore we establish a foundation element technology for future commercialization of intelligent service robots.

승강장 안전발판 시스템의 내구성 평가 (Durability Evaluation of Platform Safety Step System)

  • 박민흥;곽희만;김민호
    • 한국신뢰성학회지:신뢰성응용연구
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    • 제16권2호
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    • pp.125-133
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    • 2016
  • Purpose: The purpose of this study is to evaluate durability of platform safety step system in railway. Method: We performed finite element analysis & durability analysis of platform safety step system with VPD (Virtual Product Development) techniques and examined the durability standard & qualification life through the rig test during no failure test time in reliability qualification test. We continued to test 1 million cycles in KRS (Korea Railway Standard) for system's robust design performance. Result: FEM analysis results are 14.9MPa & 14.7MPa of pin-joint, pivot and durability analysis result is above 1 million cycles. we calculated theoretically no failure test time 855,000 cycles and through the 1 million cycles durability rig test in KRS standard we confirmed product quality. Conclusion: This platform safety step system was designed very safe in terms of a mechanical strength & durability.

Web Based Smart Home Automation Control System Design

  • Hwang, Eui-Chul
    • International Journal of Contents
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    • 제11권4호
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    • pp.70-76
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    • 2015
  • The development of technology provides and increases security as well as convenience for humans. The development of new technology directly affects the standard of life thanks to smart home automatic control systems. This paper describes a door control, automatic curtain, home security (CCTV, fire, gas, safe, etc.), home control (energy, light, ventilation, etc.) and web-based smart home automatic controller. It also describes the use of ARM (Advanced RISC Machines) for automatic control of home equipment, a Multi-Axes Servo Controller using FPGA (Field Programmable Gate Array) and PLC (programmable logic controller). Additionally, it describes the development of a HTML editor using web auto control software. The tab loading time (7 seconds) is faster when using ARM-based web browser software instead of Chrome and Firefox is used because the browser has a small memory footprint (300M). This system is realized by web auto controller language which controls and uses PLCs that are easier than existing devices. This smart home automatic control technology can control smart home equipment anywhere and anytime and provides a remote interface through mobile equipment.

디지털 원자로 보호계통의 소프트웨어 확인 및 검증 (Software Verification & Validation for Digital Reactor Protection System)

  • 박기용;권기춘
    • 대한전기학회:학술대회논문집
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    • 대한전기학회 2005년도 심포지엄 논문집 정보 및 제어부문
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    • pp.185-187
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    • 2005
  • The reactor protection system is the most important function for the safe operation of nuclear powerplants (NPPs) in that such system protects a nuclear reactor tore whose damage can cause an enormous disaster to the nuclear facility and the public. A digital reactor protection system (DRPS) is being developed in KAERI for use in the newly-constructed NPPs and also for replacing the existing analog-type reactor Protection systems. In this paper, an software verification and validation (V&V) activities for DRPS, which are independent of the DRPS development processes, are described according to the software development life cycle. The main activities of DRPS V&V processes are the software planning documentations, the verification of software requirements specification (SRS) and software design specification (SDS), the verification of codes, the tests of the integrated software and system. Moreover, the software safety analysis and the software configuration management are involved in the DRPS V&V processes. All of the V&V activities are described, in detail, in this paper.

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System Engineering 측면에서 전동차 화재기술관리 (Rolling Stock Fire Engineering aspect of System Engineering)

  • 장정훈;강찬용
    • 한국철도학회:학술대회논문집
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    • 한국철도학회 2005년도 춘계학술대회 논문집
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    • pp.163-168
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    • 2005
  • In case of rolling stock, SEMS is generally applied in the advanced countries, but is start stage in our country. SEMS is defined the system engineering management system in order to achieve the optimized train performance among the several client requirements aspect of technical engineering management during the design life cycle. And the fire engineering activities in hong kong EMU project are introduced aspect of SEMS in this paper. The fire engineering at rolling stock in view of SEMS controls to apply the satisfied interior material by the fire safety standards (regulation of the commute urban subway safety guideline by the MOCT, BS 6853, NFPA 130, NF F 16-101) and to minimize the fire load in order that passengers egress safe from the fired rolling stock. The rolling stock in the advanced countries is designed to stand for 15-20 minutes in considering the rolling stock to be fired in tunnel. For passenger fire safety, the passenger evacuation provision and progress is set up.

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고리 1호기 주기적안전성 평가 (PERIODIC SAFETY REVIEW ON KORI UNIT 1)

  • Kim, Tae-Ryong
    • 한국에너지공학회:학술대회논문집
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    • 한국에너지공학회 2003년도 춘계 학술발표회 논문집
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    • pp.403-414
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    • 2003
  • Periodic safety review on Kori Unit 1 has been successfully done for the first time in Korea. 11 safety factors of the review were fully evaluated in accordance with the domestic legal system. Although it is the oldest nuclear power plant in Korea, Kori Unit 1 was found to have maintained good operating conditions and continuously enhanced its safety by implementing post-TMI action plans and other safety issues, such as replacing steam generators and process/control system. It can be therefore confirmed that safe operation of Kori Unit 1 is guaranteed until next periodic safety review. Nevertheless, some corrective action items were recommended to enhance further its safety level, such as equipment qualification, additional ageing management program, strengthening of some procedures related to administration and human factor. The results of PSR can be utilized for the continued operation beyond the design life as long as the plant safety is maintained and improved. Experiences of the PSR on Kori Unit 1 can be also applied to PSR on other plants.

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