• 한국산업정보학회논문지
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• 제29권2호
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• pp.55-68
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• 2024

플랜트 엔지니어링 기업은 서로 다른 공종별 부서에서 플랜트 공정/설비/파이프/계장 등 각 관련 분야의 요구사항 문서를 작성하거나 참조하게 된다. 공정 관련 요구사항 문서는 공정에 대한 설명과 함께 이를 운영할 설비 또는 관련 시설의 요구사항들을 포함한다. 각 공종별 문서에 기술된 설비 또는 부품에 관련된 요구사항과 사양 정보는 문서의 작성자와 검토자들이 다르기 때문에 상호 간에 불일치가 발생할 가능성이 있다. 이 사항들에 대한 일치성을 확인하는 것은 전체 플랜트 설계 정보의 신뢰도를 높일 수 있다. 하지만, 문서의 양이 방대하고 서로 다른 문서들에 동일한 설비 부품에 대한 요구사항들이 일반 문장 형태로 흩어져 있기에 이를 사람이 추적하여 관리하는 것은 한계가 있다. 본 논문에서는 서로 다른 문서들 내에 기술된 요구사항 문장들을 분석하여 설비 또는 설비 부품과 관련된 요구사항 문장의 유사도를 계산하여 의미적으로 동일한 문장을 찾아내는 방법을 제안한다. 요구사항 문장의 유사도를 계산하기 위하여 의미적으로 요구사항의 중심이 되는 부품과 속성을 개체명 인식 방법을 활용하여 찾아내고, 찾아진 부품과 속성들의 유사도를 계산하여 두문장이 의미적으로 동일함을 판단하는 방법을 제안한다. 플랜트 현장에서 사용하는 문서의 문장들을 예제로 하여 제안하는 방법을 설명하고 실험 결과를 설명한다.

• Nuclear Engineering and Technology
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• 제55권2호
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• pp.421-431
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• 2023

Nuclear power plants (NPPs) have technical specifications (Tech Specs) to ensure that the equipment and key operating parameters necessary for the safe operation of the power plant are maintained within limiting conditions for operation (LCO) determined by a safety analysis. The LCO of Tech Specs that identify the lowest functional capability of equipment required for safe operation for a facility must be complied for the safe operation of NPP. There have been previous studies to aid in compliance with LCO relevant to rule-based expert systems; however, there is an obvious limit to expert systems for implementing the rules for many situations related to LCO. Therefore, in this study, we present a retrieval methodology for similar LCO cases in determining whether LCO is met or not met. To reflect the natural language processing of NPP features, a domain dictionary was built, and the optimal term frequency-inverse document frequency variant was selected. The retrieval performance was improved by adding a Boolean retrieval model based on terms related to the LCO in addition to the vector space model. The developed domain dictionary and retrieval methodology are expected to be exceedingly useful in determining whether LCO is met.

• 한국안전학회지
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• 제36권5호
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• pp.79-85
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• 2021

A standard engineering model that reflects the current organization system and engineering operation process of domestic nuclear power plants was developed based on the Standard Nuclear Performance Model developed by the American Nuclear Energy Association. The level 0 screen, which is the main screen of the engineering model computer system, consisted of an object tree structure, which provided information that is phased down from a higher structure level to a lower structure level (i.e., level 3). The level 1 screen provided information related to the sub-process of the engineering operation, whereas the Level 2 screen provided information related to each engineering operation activity. In addition, the Level 2 screen provided additional functions, such as linking electronic procedures/guidelines, providing electronic performance forms, and connecting legacy computer systems (such as total equipment reliability monitoring system, configuration management systems, technical information systems, risk monitoring systems, regulatory information, and electronic drawing system). This screen level increased the convenience of user's engineering tasks by implementing them. The computerization of an engineering model that connects the entire engineering tasks of an establishment enables the easy understanding of information related to the engineering process before and after the operation, and builds a foundation for the enhancement of the work efficiency and employee capacity. In addition, KHNP developed an online training module, which operates as an e-learning process, on the overview and utilization of a standard engineering model to expand the understanding of standard engineering models by plant employees and to secure competitiveness.

• 한국소음진동공학회:학술대회논문집
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• 한국소음진동공학회 2008년도 춘계학술대회논문집
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• pp.59-62
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• 2008

This paper presents the procedure and the results of modal identification testing of a seismic monitoring system central processing unit cabinet for a nuclear power plant. This paper also provides a model updating for making effective analytical modeling of cabinet-type electrical equipment by comparing the test results with the analysis results. From the test results and their interpretation, modal properties (modal frequency, mode shape, and modal damping) of the specimen were satisfactorily identified. However, the analysis results may need to study further to find the effective and presentative model for the cabinet-type electrical equipment. This paper just presents the first stage of the research project "Development of dynamic behavior analysis technique of dynamic structure system" which is trying to build the lumped mass beam stick model even their results do not agree well with the test results.

• 에너지공학
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• 제23권1호
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• pp.90-94
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• 2014

본 논문은 원자력발전소의 내환경기기검증(EQ)을 위한 HVAC 과도분석 방법에 대한 내용을 기술하고 있다. 분석 대상 격실은 비안전관련 HVAC 계통에 의해 공급되는 격실 중에 원자로 안전정지를 담당하는 중요기기가 위치한 구역/격실을 선정하였다. 그리고 해당 HVAC 계통이 공급되는 건물별로 HVAC 과도시 온도조건을 분석하였다. 본 분석을 위해서 GOTHIC 전산코드를 사용하였다. 온도분석 결과는 원자로 보조건물 환기계통(DVN)의 W315/W415 격실에서 $82.2^{\circ}C$로 가장 높은 온도값을 나타내며, 제어봉구동장치 전원공급건물 및 보조급수펌프실(DVG) 계통의 W229 (Auxiliary feedwater pump room) 격실에서 $52.7^{\circ}C$, 기기냉각건물 환기계통(DVI)의 전 격실에서 $42.9^{\circ}C$, 전기건물 주환기 계통(DVL)의 L207 (Hot workshop) 격실에서 $57.3^{\circ}C$를 각각 나타났다. 이러한 온도값은 일반적인 원전의 기기검증 제한값인 $171^{\circ}C$이하이므로 내환경검증 요건을 만족하는 온도이다.

• 한국지진공학회논문집
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• 제25권6호
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• pp.261-266
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• 2021

Nuclear power plants in Korea were designed and evaluated based on the NRC's Regulatory Guide 1.60, a design response spectrum for nuclear power plants. However, it can be seen that the seismic motion characteristics are different when analyzing the Gyeongju earthquake and the Pohang earthquake that has recently occurred in Korea. Compared to the design response spectrum, seismic motion characteristics in Korea have a larger spectral acceleration in the high-frequency region. Therefore, in the case of equipment with a high natural frequency installed in a nuclear power plant, seismic performance may be reduced by reflecting the characteristics of domestic seismic motions. The failure modes of the equipment are typically structural failure and functional failure, with an anchorage failure being a representative type of structural failure. In this study, comparative analyses were performed to decide whether to consider the inelastic behavior of the anchorage or not. As a result, it was confirmed that the seismic performance of the anchorages could be increased by considering the inelastic behavior of an anchorage.

• 한국화재소방학회논문지
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• 제30권3호
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• pp.79-85
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• 2016

원자력발전소의 방화지역에서 전기적인 단락, 지락, 전기회로 개방 등의 전기 문제로 화재가 발생할 수 있다. 전기 화재가 발생할 경우 안전계통 및 관련기기의 안전정지 기능이 상실된다. 이러한 사고를 예방하기 위하여 안전계통은 다중성, 독립성으로 설계되어 있다. 그러나 케이블 화재시 운전원은 오동작, 잘못된 지시 및 계측으로 발전소 상황을 잘 못 판단하여 적절한 조치를 하지 못할 수 있다. 따라서 주제어실 화재시 케이블 기능상실온도에서 최소 운전원 조치 요구시간인 5분은 매우 중요하다. 본 논문에서 주제어실 화재시 케이블의 기능상실온도 시간을 분석하여 운전원 조치시간이 충분한지 평가하여 주제어실 화재에 대한 안전성을 확인하였다.

• 방사성폐기물학회지
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• 제16권3호
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• pp.389-396
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• 2018

국내 가동원전 중 2-루프 가압경수로인 고리1호기는 약 40년 운전한 후, 2017년 6월 18일 영구정지되었다. 영구정지된 고리 1호기는 주요 해체작업을 수행하기전에 계통내 선량률을 저감시켜 작업자피폭을 최소화하기 위한 계통제염을 수행할 예정이다. 일반적으로, 계통제염 범위는 원자로압력용기, 가압기, 증기발생기, 화학 및 체적제어계통, 잔열제거계통 및 원자로 냉각재계통 주요배관을 포함한다. 이러한 계통 및 기기 등을 효율적으로 제염하기 위해서는 제염과정에서 원자로냉각재계통내 유동특성을 평가할 필요가 있다. 계통제염을 위해 순환유량을 제공하는 방법은 다양하나, 본 논문에서는 잔열제거펌프 운전에 따른 고리1호기 원자로냉각재계통내 유동특성을 평가하였다. 잔열제거펌프를 이용한 계통제염은 원자로냉각재 내 유량의 불균형을 초래하여 계통내 기기 및 배관 등에 불순물을 침적시켜 제염이 효율적이지 않다는 것으로 평가되었다.

• 설비공학논문집
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• 제11권3호
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• pp.301-312
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• 1999

Experiments were carried out to evaluate performance of the cold air distribution systems with an ice storage tank in test room. Cold air distribution systems provide primary air for comfort conditioning or process cooling at coil discharge temperatures$4^{\circ}C$ to$11^{\circ}C$. The application of a cold air distribution system allows for the downsizing of air distribution equipment and central plant equipment when ice storage tank is used. The benefit of a cold air distribution system include a decrease in the floor-to-floor height, increase floor space, reduced building capital costs, reduced energy use and demand. The use of cold air distribution can result in the most cost effective system and is currently being implemented world wise as the new standard in air conditioning systems. In this study, the cold air distribution system is compared with the general ice storage system. Under the same cooling load conditions, experimental results show that the supply air volume of cold air distribution system decrease 38%, and decrease 45% flow rate of brine for the general ice storage system.

• 대한산업공학회지
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• 제39권6호
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• pp.599-608
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• 2013

This study is intended to propose optimal maintenance organization to process industry, especially paper industry by analyzing maintenance organization of paper industry and finding out how the maintenance organization and the allocation of maintenance resources influence maintenance performance indices here in this paper. In this study, we analyzed the maintenance organization in detail and studied correlation between maintenance organization and equipment failure rate for the major top six domestic paper-mills in market share. According to the study, the maintenance organization has been changed in accordance with its business environment, but its performance was different by both the allocation way of maintenance resources and the structure of maintenance organization. For paper industry, whose availability is the most important key index that determines the success or failure of a business, it turns out to be the most effective strategy that operates the combination maintenance combined central maintenance with area maintenance and allocates the maintenance resources mainly for preventive maintenance. In particular, it turned out to be that there is the strong positive correlation between the rate of shift workers and the equipment failure rate. The results of this study is not limited to paper industry, but expandable to other industry. So it is expected that the direction of the maintenance organization would be given to the company which is struggling to improve its availability.