• 대한안전경영과학회지
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• 제17권3호
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• pp.33-44
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• 2015

Domestic plant construction sites have a tendency to become bigger, more various and complicated. Moreover frequency of industrial incident is increasing due to short project period, coexistence work condition and using heavy construction equipment. Installing safety facilities and safety training contribute to prevent incident. But mostly incident happens due to workers' unsafe action and wrong work method. Technically, it is very difficult for us to closely manage workers preventing incident. Therefore, the role of foreman who ordinarily works together with his workers is considered more important. Specific execution plan was drawn through industrial incident statistics from Ministry of Labor and questionnaire survey to interest parties(supervisor, safety staff and foreman). If foreman has raised sense of belonging and responsibility by conducting practical safety training for his workers, manages job site and receives proper compensation for these roles, it will be expected that it fully influences incident decrease.

• 한국가스학회지
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• 제23권2호
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• pp.55-60
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• 2019

가상현실 기술을 이용한 플랜트 안전훈련 시스템 개발을 위해서 대규모 플랜트를 대상으로 훈련 시스템을 구성하였다. 소규모 플랜트 또는 단위장치의 안전훈련에 비해서 가상 플랜트 구현, 공정 내 데이터 처리, 작업 지시 등 많은 시스템 구성이 필요하며 이들에 대한 통합 시스템 작업을 진행 하였다. 대상 플랜트인 RDS 공정은 고온 고압의 위험도가 높은 공정으로 해당 범위에서 누출로 인한 화재가 발생할 경우에 조치할 수 있는 훈련 시나리오를 고려하였으며 실제 사용 중인 운전 정지 절차를 참조하였다. 제안한 안전훈련 통합 시스템은 RDS 공정에서 일어날 수 있는 유사 상황에서도 이용 가능하며 대규모 플랜트에서의 가상현실을 이용한 안전훈련의 새로운 플랫폼으로 고려될 수 있다.

• 안전기술
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• 통권140호
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• pp.64-71
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• 2009

• Nuclear Engineering and Technology
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• 제52권9호
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• pp.1983-1989
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• 2020

The human reliability analysis is a method by which, in general terms, the human impact to the safety and risk of a nuclear power plant operation can be modelled, quantified and analysed. It is an indispensable element of the PSA process within the nuclear industry nowadays. The paper herein presents a sensitivity study of the human reliability analysis performed on a real nuclear power plant-specific probabilistic safety assessment model. The analysis is performed on a pre-selected set of post-initiator operator actions. The purpose of the study is to investigate the impact of these operator actions on the plant risk by altering their corresponding human error probabilities in a wide spectrum. The results direct the fact that the future effort should be focused on maintaining the current human reliability level, i.e. not letting it worsen, rather than improving it.

• 대한전기학회:학술대회논문집
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• 대한전기학회 2001년도 합동 추계학술대회 논문집 정보 및 제어부문
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• pp.201-203
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• 2001

Safety is emphasized in nuclear power plant system for its characteristic. One of the most important systems to guarantee the safety of nuclear power plant is the PPS(Power protection system). The measurement control system includes PPS, which is similar to the human nervous system, is very important factor not only for the safety but also for the operation. Therefore, developing a technology to level up the performance of measurement system and reliability of the plant will bring cost-effective and safe generation of nuclear power. In this study, I researched composition of digitized PPS and algorithm for cyclic inspection.

• 전기학회논문지
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• 제61권6호
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• pp.859-864
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• 2012

The computer network plays an important role in modern digital controllers within a safety system of a nuclear power plant. For the reliable and realtime data communication between controllers, this paper proposes a modified high-reliable MVB(multi-function vehicle bus) as a main control network for a safety system of a nuclear power plant. The proposed network supports the state-based communication in order to ensure the deterministic communication latency, and very fast network recovery when the bus master fails compare to the standard MVB. This paper also shows the implementation results using a FPGA-based testbed.

• 대한안전경영과학회지
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• 제9권1호
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• pp.51-63
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• 2007

It is noted that the disaster such as fire, explosion, collapse has been rapidly increased caused by strength deterioration of steel structures at petrochemical plant during fire. In this regard, it is stressed out that the legal requirement for fire proofing for steel structures at petrochemical plant should be carefully reviewed since the current legal requirement such as Industrial Safety & Health Law, Architectural Law has a conflict and different way of approach. In addition, it is our point of view that the present law should be revised to consolidate into single law including engineering design criteria to reflect unreasonable legal requirement. It is further our point of view that the performance certificate for fire proofing like UL-1709, basis of maintenance should be appropriately and reasonably provided in line with global practice.

• Nuclear Engineering and Technology
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• 제48권6호
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• pp.1404-1411
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• 2016

Pipe wall thinning in the secondary piping system of a nuclear power plant is currently a major problem that typically affects the safety and reliability of the nuclear power plant directly. Regular in-service inspections are carried out to manage the piping system only during the overhaul. Online thickness monitoring is necessary to avoid abrupt breakage due to wall thinning. To this end, a transducer that can withstand a high-temperature environment and should be installed under the insulation layer. We propose a thin plate type of embedded ultrasonic transducer based on magnetostriction. The transducer was designed and fabricated to measure the thickness of a pipe under a high-temperature condition. A number of experimental results confirmed the validity of the present transducer.

• 한국안전학회지
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• 제28권3호
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• pp.44-50
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• 2013

Process gas piping is one of the most basic components frequently used in the refinery and petrochemical plants. Many kinds of by-product gas have been used as fuel in the process plants. In some plants, natural gas is additionally introduced and mixed with the byproduct gas for upgrading the fuel. In this case, safety or design margin of the changed piping system of the plant should be re-evaluated based on a proper design code such as ASME or API codes since internal pressure, temperature and gas compositions are different from the original plant design conditions. In this study, series of piping stress analysis were conducted for a process piping used for transporting the mixed gas of the by-product gas and the natural gas from a mixing drum to a knock-out drum in a refinery plant. The analysed piping section had been actually installed in a domestic industry and needed safety audit since the design condition was changed. Pipe locations of the maximum system stress and displacement were determined, which can be candidate inspection and safety monitoring points during the upcoming operation period. For studying the effects of outside air temperature to safety the additional stress analysis were conducted for various temperatures in $0{\sim}30^{\circ}C$. Effects of the friction coefficient between the pipe and support were also investigated showing a proper choice if the friction coefficient is important. The maximum system stresses were occurred mainly at elbow, tee and support locations, which shows the thermal load contributes considerably to the system stress rather than the internal pressure or the gravity loads.

• 한국안전학회지
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• 제7권4호
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• pp.33-43
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• 1992

A methodology to develop an expert system for chemical plant fault diagnosis based on functional-structure of chemical plant is proposed. A methodology to generalize and utilize the heuristic know-edge of plant operators is also developed. A plant can be seen as a Hierarchical set of subsystems. Each subsystem is called a SCOPE. The state of the plant and the behavior of each subsystem is managed by the SCOPES. An expert system based on this functional structure and knowledge base has been developed and ar plied to the subprocess of etylene plant to evaluate the effectiveness of the methodology.