• Journal of the Korean Society of Safety
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• v.26 no.4
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• pp.14-19
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• 2011

Conveyors cause a high serious and fatal injuries in the industry. Every year people are hurt or killed as a result of accidents on conveyors. Most accidents occur during operation and maintenance when employees are working on moving, unguarded conveyors or when the conveyors starts unexpectedly. In 2008 there were 486 reported injures ranging from fatalities to injures. Of these 486 reported accidents, 8 were fatalities, 66.9%(325) of reported accidents occurred in manufacturing company and 43.8%(213) occurred at the belt conveyors. The objective of this study was to invent the remote emergency stop device because industrial accidents mainly occur at blind spots where usually do not have any safety guard or device rather than the normal working places. In principle, this new device will use with the existing safety system. Then, it will be powerful safety system for preventing injuries related with conveyors.

• Proceedings of the Korean Institute of Navigation and Port Research Conference
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• 2020.11a
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• pp.157-158
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• 2020

항만용 자율주행 야드트럭운행 환경은 무신호교차로 주행, 낮은 GPS정확도, 악천후상황주행, 이송 컨테이너 위치변경등과 같이 일반 도로의 센서기반의 자율주행차량 운행과 다르게 매우 복잡하다. 이를 위해서는 항만내 특성을 반영한 실시간 위치, 속도 등에 대한 정확한 인식이 중요한 요소이다. 이를 위해서 센서융합과 V2X기반의 복합적인 항만용 실시간 로컬 동적지도 (Local Dynamic Map) 생성 및 V2X기반의 협력측위를 통하여서 기존의 독립적인 자율주행차량의 위치 인식보다 더 개선된 고정밀 위치 인식 정보추출이 필요하다. 본 연구에서는 복합적인 항만용 동적지도 생성관리시스템의 설계 방안 및 협력측위 기술 적용 방안을 제시하고 이를 활용한 항만 구역내 자율주행차량 및 모든 화물 이송장비들의 실시간 위치 인식뿐만 아니라 이동체의 사전 충돌예측 및 비상정지 안전 제어 가능한 V2X 기반의 인텔리젼스 한 3차원 관제시스템 설계 방안을 제시하고자 한다.

• Journal of the Korean Society of Marine Environment & Safety
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• v.30 no.4
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• pp.317-323
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• 2024

According to the section A-VI/3 of the International Convention on Standards of Training, Certification and Watchkeeping for Seafarers (STCW), Water-based firefighting training center is mandatory to obtain onboard certificates. This space, being similar to fire situations on ships requires that safety measures be quantified to ensure occupant safety and establish operational standards. For fire safety evaluation, cases were designed based on the presence or absence of smoke control equipment using Pyrosim based on Fire Dynamics Simulation (FDS). Vector analysis was performed to evaluate flow of smoke and heat. Available safe escape time / required safe escpae time (ASET/RSET) analysis was conducted to evaluate safety by comparing the interpreted numerical results through Pathfinder. During safety evaluation of the current operational condition, the appropriateness of the function of each smoke control equipment was numerically and visually indicated. The emergency situation with dust collector stopped was expressed by each evacuation time and safety margin of 111.2 seconds, suggesting that be used as a standard of evacuation time.

• Nuclear Engineering and Technology
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• v.26 no.1
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• pp.9-18
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• 1994

The engineered safeguards of Wolsung nuclear power plant unit 1 contain redundant systems of 2-out-of-3 logic which are not operating under normal conditions but are called upon to act when emergency conditions develop. To ensure their operability, the systems are periodically tested. In this work, we develop the unavailability formulae for 2-out-of-3 logic configurations which take into account the failure probability of the channels tested due to human error in the simultaneous testing scheme. We also develop the model for the probability that the reactor is tripped during the surveillance test due to either system failure or human error. We determined the optimal inspection periods of safety systems, taking into account both the unavailability of the safety system and the probability that the reactor is tripped during the surveillance test. We compared the results with the inspection periods currently used at Wolsung NPP Unit 1. As a result, the inspection periods obtained using a minimum human error (8.24 $\times$ 1$^{-6}$ ) are shorter than those currently used in Wolsung NPP unit 1 whereas the inspection periods obtained using a maximum human error are (4.44 $\times$ 10$^{-4}$ ) longer than those used in Wolsung NPP unit 1.

• Proceedings of the Korean Institute of Information and Commucation Sciences Conference
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• 2016.10a
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• pp.819-820
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• 2016

Electrical power distribution is consists of high voltage, low voltage and motor control center(MCC). Motor control centers involves turning the motor on and off, it is configured electronic over current relay to detect a motor overcurrent flows. Existing electronic over current relay detects electrical fault such as overcurrent, undercurrent, phase sequence, negative sequence current, current unbalance and earth fault. However, it is difficult to detect mechanical fault such as locked rotor, motor stator and rotor and bearing fault. In this paper, we propose a condition monitoring and fault diagnosis system for electrical and mechanical fault detection of rotating machinery. The proposed system is designed with signal input and control part, system interface part and data acquisition board for condition monitoring and fault diagnosis, it was possible to detect electrical fault and mechanical fault through measurement and control of insulation resistance, locked rotor, MC counter and bearing temperature.

• Proceedings of the KIEE Conference
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• 2011.07a
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• pp.214-215
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• 2011

2대의 교류발전기 G1과 G2가 병렬운전 중 일 때 내부 기전력 E1, E2는 같은 위상이지만, 크기가 E1>E2로 될 때 두 발전기 사이에는 전위차가 있으므로 횡류 Ic가 흐르게 된다. 남강수력발전소는 주변압기(15MVA, 3.45/66kV) 한대에 수차발전기(7MVA) 2대가 병렬로 운전 중인데, 남강수력 제1호 수차발전기 AVR 시스템의 고장(RS 1기판)으로 G1 발전기의 내부 유기전압과 G2 발전기의 내부 유기전압에 차가 생기고, 이 양자의 차 전압을 전원으로 하여 발전기 G1과 G2를 환류하는 전류가 발생하여 발전 기동 중 비상정지 하였다. 본 논문에서는 고장원인 분석과정 및 AVR 시스템 보수 전 후 파형 비교 및 사고원인을 논하고자 한다.

• Transactions of the Korean Society of Pressure Vessels and Piping
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• v.12 no.1
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• pp.134-140
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• 2016

The Control Rod Assembly (CRA) controls the reactor power by adjusting its position in the reactor core during normal operation and should be quickly inserted into the reactor core by free drop under scram condition to shut down chain reactions. Therefore, the drop time of the CRA is one of important factors for the safety of the nuclear reactor and must be experimentally verified. This study presents the drop performance test of the CRA which has been conceptually designed for the Proto-type Generation IV Sodium-cooled Fast Reactor. During the test, the CRA was free dropped from a height of 1 m under different flow rate conditions and its drop time was measured. The results showed that the drop time of the CRA increased as the flow rate increased; the average drop times of the CRA were approximately 1.527 seconds, 1.599 seconds and 1.676 seconds at 0%, 100% and 200% of design flow rates, respectively.

• Proceedings of the Korean Society of Propulsion Engineers Conference
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• 2011.11a
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• pp.379-382
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• 2011

Engine test as well as unload test of starting motor itself was performed to evaluate the braking characteristics of starting system used for initial spin-up of gas turbine for power generation. Through the experimental evaluation of the braking performance with the capacity of braking resistor of the starting motor, we have achieved quantitative data to secure robust braking characteristics in emergency during the starting period of the gas turbine. It is possible to establish a capacity selection criterion of braking resistor to ensure the starting reliability of the gas turbine.

• The KSFM Journal of Fluid Machinery
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• v.12 no.5
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• pp.19-24
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• 2009

This paper is performed to find out the stability of water-hammer in pipe line and pump station that is happened when additional water needs demanded. At first, the water supply construction project is planned to supply $6,000\;m^3/day$ through 17.9 km pipe line. But additional demand ($1,200\;m^3/day$) happened from Cheong-ra water reservoir. In this situation, air-chamber($4\;m^3$) and vacuum breaker valve(${\varphi}100\;mm$) are needed to prevent water-hammer. When the additional water is supplied, the existing facilities (air-chamber, vacuum breaker valve) are sufficient to alleviate shock not changing capacity alteration, judging from the airspace change and rise. Therefore, there is no problem for water-hammer by installing air-chamber($4\;m^3$) and vacuum breaker valve(${\varphi}100\;mm$) at the top of Yeo-ju hill.

• The Safety technology
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• no.190
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• pp.14-17
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• 2013

원자력발전소 의존도가 높은 우리나라의 경우 원전 가동상태에 따라 전력 수급 문제가 큰 영향을 받게 된다. 올해 여름 부품비리, 부실정비 등의 사건으로 일부 원전이 가동 정지되면서 발생한 '비상 전력수급체계 운영'이 그 대표적인 예다. 이처럼 국가 전반에 미치는 파급영향이 크기 때문에 원전의 안정적인 운영은 선택이 아닌 필수라고 할 수 있다. 그럼 원전을 안정적으로 운영하려면 어떻게 해야 할까. 누구나 알고 있듯, 그에 대한 해답은 '철저한 안전관리'와 '완벽한 정비'다. 하지만 원전의 경우 워낙 시설규모가 크고, 다양한 산업이 집약돼 있다 보니 체계적인 안전활동을 전개하기가 상당히 어렵다. 그런데 이 같은 점에도 불구, 원전 내에서 빈틈없는 안전관리를 펼치고 있는 안전관리자들이 있어 주목을 받고 있다. 그 주인공은 바로 경북 울진 한울원자력본부 내에 위치한 한전KPS 한울 제1~3사업소의 박이현 과장(1사업소), 이상헌 과장(2사업소), 강경석 과장(3사업소)이다. 이들은 모두 관련 경력만 20여 년에 달하는 베테랑으로, 원전설비 관련 안전관리에 있어서는 타의 추종을 불허하는 실력을 갖추고 있다. 연이은 원전 사건사고로 높아진 국민들의 우려를 씻어내기 위해 더욱 열심히 안전관리에 매진하고 있다는 이 3명의 안전관리자들을 만나 이야기를 나누어 봤다.