• International Journal of Quality Innovation
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• 제7권2호
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• pp.97-124
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• 2006

The purpose of this research is to create an expert risk-based piping system inspection model. The proposed system includes a risk-based piping inspection system and a piping inspection guideline system. The research procedure consists of three parts: the risk-based inspection model, the risk-based piping inspection model, and the piping inspection guideline system model. In this research procedure, a field plant visit is conducted to collect the related domestic information (Taiwan) and foreign standards and regulations for creating a strategic risk-based piping inspection and analysis system in accordance with the piping damage characteristics in the petrochemical industry. In accordance with various piping damage models and damage positions, petrochemical plants provide the optimal piping inspection planning tool for efficient piping risk prediction for enhancing plant operation safety.

• Nuclear Engineering and Technology
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• 제50권8호
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• pp.1210-1216
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• 2018

Site or multi-unit (MU) risk assessment has been a major issue in the field of nuclear safety study since the Fukushima accident in 2011. There have been few methods or experiences for MU risk assessment because the Fukushima accident was the first real MU accident and before the accident, there was little expectation of the possibility that an MU accident will occur. In addition to the lack of experience of MU risk assessment, since an MU nuclear power plant site is usually very complex to analyze as a whole, it was considered that a systematic method such as probabilistic safety assessment (PSA) is difficult to apply to MU risk assessment. This paper proposes a new MU risk assessment methodology by using the conventional PSA methodology which is widely used in nuclear power plant risk assessment. The logical failure structure of a site with multiple units is suggested from the definition of site risk, and a decomposition method is applied to identify specific MU failure scenarios.

• 한국연소학회지
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• 제20권1호
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• pp.1-5
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• 2015

Fire and explosion analysis are performed for the quantitative risk assessment on the LNG test plant. From the analysis for a case of fire due to large leakage of LNG from the tank, it is obtained that loss of lives can be occurred within the radius of 60 m from the fire origin. Specially, wind can extend the extent of damage. Because the LNG test plant is not enclosed, the explosion overpressure is less than 6 kPa and the explosion has little effect on the integrity of the LNG test plant.

• 시스템엔지니어링학술지
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• 제4권1호
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• pp.19-29
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• 2008

Traditionally gas plant R&D has had a world-wide weak position in terms of high technology. Especially System engineering did not exactly apply to gas plant construction. So, Gas Plant R&D Center is determined to make the establishment of the system engineering for the standard of gas plant. Gas Plant R&D Center has two projects. Firstly, the establishment of the R&D management system. Secondly, the system engineering which is included in the VE concept of EPC parts. But Gas Plant R&D Center exists in the particular conditions for successful development of the new process and core equipments. Now we will describe the establishment of R&D management system and particular conditions(Risk Conditions) for gas plant.

• 한국건설관리학회논문집
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• 제17권1호
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• pp.18-27
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• 2016

본 연구는 플랜트 시공 현장의 안전성 확보를 위한 플랜트 시공단계의 주요 위험요인 분류 및 위험요인별 중요도 분석을 목적으로 수행되었다. 플랜트 산업은 지속적인 호황과 증가로 해외 플랜트 수주 실적이 2014년에는 전체 수주금액의 61% 증가한 실적을 보였듯이 플랜트 산업은 시공 단계의 위험요인, 안전관리 대상 인식 및 요인별 중요도 등으로 다양한 사고 예방 및 안전관리 개발과 도입이 필요한 실정이다. 이를 위해 플랜트 시공단계의 재해현황 자료 수집 및 국내 플랜트 시공관련 전문가를 대상으로 1차 조사 분석을 수행하여 플랜트 시공단계의 위험요인을 4M의 4가지 관리요인으로 분류하였다. 이후 AHP 기법을 적용하기 위해 국내 플랜트 시공 및 안전관련 전문가를 대상으로 2차 조사 분석을 수행하였다. 2차 분석결과를 바탕으로 위험요인별 중요도 및 순위를 분석하여 제시하였다. 본 연구는 플랜트 시공단계의 주요 위험요인을 사전에 파악하여 인식하고 이를 예방하기 위한 기초 자료로써 활용하고자 한다.

• 한국연소학회:학술대회논문집
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• 한국연소학회 2014년도 제49회 KOSCO SYMPOSIUM 초록집
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• pp.331-332
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• 2014

Underground power plant is required the strict safety management and safety assessment. Because it is the high risk of explosion by characteristic of enclosed space. In case gas leak of enclosed space, the ventilation facilities is very important in order to prevent explosion by the maintain less than the LEL(lower explosive limit). Thus, Through a safety assessment of ventilation volume is to reduce the risk for ventilation facilities in Underground power plant.

• Nuclear Engineering and Technology
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• 제53권1호
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• pp.103-110
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• 2021

In the development of a Risk Monitor probabilistic safety assessment (PSA) model from the basic PSA model of a nuclear power plant, the modeling of common-cause failure (CCF) is very important. At present, some approximate modeling methods are widely used, but there lacks criterion of modeling accuracy and error analysis. In this paper, aiming at ensuring the accuracy of risk assessment and minimizing the Risk Monitor PSA models size, we present three basic issues of CCF model resulted from the changes of a nuclear power plant configuration, put forward corresponding modeling methods, and derive accuracy criteria of CCF modeling based on minimum cut sets and risk indicators according to the requirements of risk monitoring. Finally, a nuclear power plant Risk Monitor PSA model is taken as an example to demonstrate the effectiveness of the proposed modeling method and accuracy criteria, and the application scope of the idea of this paper is also discussed.

• 한국지진공학회논문집
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• 제25권2호
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• pp.53-58
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• 2021

Nuclear power plant's safety against seismic events is evaluated as risk values by probabilistic seismic safety assessment. The risk values vary by the seismic failure correlation between the structures, systems, and components (SSCs). However, most probabilistic seismic safety assessments idealized the seismic failure correlation between the SSCs as entirely dependent or independent. Such a consideration results in an inaccurate assessment result not reflecting real physical phenomenon. A nuclear power plant's seismic risk should be calculated with the appropriate seismic failure correlation coefficient between the SSCs for a reasonable outcome. An accident scenario that has an enormous impact on a nuclear power plant's seismic risk was selected. Moreover, the probabilistic seismic response analyses of a nuclear power plant were performed to derive appropriate seismic failure correlations between SSCs. Based on the analysis results, the seismic failure correlation coefficient between SSCs was derived, and the seismic fragility curve and core damage frequency of the loss of essential power event were calculated. Results were compared with the seismic fragility and core damage frequency of assuming the seismic failure correlations between SSCs were independent and entirely dependent.

• 한국자원식물학회지
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• 제33권3호
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• pp.200-219
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• 2020

We performed taxonomic reviews and habitat circumstances survey for 41 un-introduced environmentally harmful plants (as designated by the Ministry of Environment, Korea in 2016). For this purpose, we investigated plant specimens from several herbaria and performed a field survey in the southeastern region of the United States. Base on the result, we presented the most comprehensive results of weed risk evaluation and taxonomic description up to now as well as classification keys for 11 species to apply the regulation management of putative invasive alien species - Centaurea maculosa Lam., Centaurea diffusa Lam., Mikania micrantha Kunth. (Asteraceae), Cenchrus echinatus L., Neyraudia reynaudiana (Kunth) Keng ex Hitchcock, Brachiaria mutica (Forsskål) Stapf, Vulpia bromoides (L.) Gray, Lolium persicum Boissier & Hohennacker, Setaria palmifolia (J. Konig) Stapf (Poaceae), Prosopis glandulosa Torr. (Fabaceae), Fallopia baldschuanica (Regel) Hobub. (Polygonaceae).

• 한국화재소방학회논문지
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• 제7권1호
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• pp.17-29
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• 1993

본 연구는 석유/화학공장에서의 위험성 평가에 관한 것으로써, 특히 물질과 공정의 위험에 관한 상대적 평가를 수행할 수 있는 방법을 제시하였다. 즉, 물질의 위험과, 공정이 내포하고 있는 위험을 각각 고려하여 이를 종합화하였으며, 최종적으로 화재, 폭발 지수를 산정하였다. 물질계수는 인화성과 반응성으로 산정하였고, 공정 지수는 penalty라 부르는 경험적 수치를 사용하였다. 이 F&EI는 전 공정에 적용하여 위험의 상대적 평가를 실시할 수 있으며 현장에서의 직접 적용도 가능하다.