• Nuclear Engineering and Technology
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• 제37권3호
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• pp.265-272
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• 2005

Severe accidents in nuclear power plants can cause hydrogen-generating chemical reactions, which create the danger of hydrogen combustion and thus threaten containment integrity. For containment analyses, a three-dimensional mechanistic code, GOTHIC-3D has been applied near source compartments to predict whether or not highly reactive gas mixtures can form during an accident with the hydrogen mitigation system working. To assess the code applicability to hydrogen combustion analysis, this paper presents the numerical calculation results of GOTHIC-3D for various hydrogen combustion experiments, including FLAME, LSVCTF, and SNU-2D. In this study, a technical base for the modeling oflarge- and small-scale facilities was introduced through sensitivity studies on cell size and bum modeling parameters. Use of a turbulent bum option of the eddy dissipation concept enabled scale-free applications. Lowering the bum parameter values for the flame thickness and the bum temperature limit resulted in a larger flame velocity. When applied to hydrogen combustion analysis, this study revealed that the GOTHIC-3D code is generally able to predict the combustion phenomena with its default bum modeling parameters for large-scale facilities. However, the code needs further modifications of its bum modeling parameters to be applied to either small-scale facilities or extremely fast transients.

• 한국화재소방학회논문지
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• 제23권5호
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• pp.32-42
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• 2009

본 연구는 국내의 화재조사전문교육 운영 실태를 분석하고 개선방안을 도출하는데 있다. 연구결과 현재의 화재조사전문교육은 공적영역(소방, 경찰, 전기안전공사, 가스안전공사 등) 중심으로 이루어지고 있으며 중앙소방학교에서 실시하고 있는 교육이 가장 체계적인 것으로 나타났다. 그리고 사적영역(화재피해이재민, 일반국민 등)을 대상으로 하는 화재조사전문교육은 거의 이루어지고 있지 않는 것으로 나타났다. 이러한 문제점을 개선하기 위해서 현행 중앙소방학교를 평생교육체제로 전환하여 대학의 학위과정과 연계하고 소방방재청에서 시행하고 있는 화재조사관자격증 제도를 외부에 개방 및 학습수준별 5단계로 나누어 운영할 것을 제안하였다.

• 한국압력기기공학회 논문집
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• 제7권3호
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• pp.23-29
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• 2011

The renewed global interest in nuclear power has arisen from the need to reduce greenhouse gas emissions and to provide sufficient electricity for a growing global population before the accident at Fukushima Dai-ichi nuclear power plant in Japan. In spite of the safety issues of nuclear power plants raised by the ongoing Japanese nuclear crisis, many countries with nuclear power plants (NPPs) are still implementing license extensions of 10~20 years, and even consideration is being given to the concept of life-beyond-60, a further period of license extension from 60 to 80 years. To solving the materials aging problem is integral to its success. To evaluate the plant aging phenomena, a lot of background information such as materials and environment of the parts of the reactor and plant systems is needed by the experts. Information on degradation mechanisms is also used. In this paper, a materials degradation evaluation program called OnMDE-SYS (On-line Materials Degradation Evaluation System) is introduced. The developed program provides a variety of information on the materials and stressors as well as operational experience to the experts. It is also anticipated that the experts can perform materials degradation assessment on the web directly by referring to domestic and international information about the degradation of a nuclear power plants through OnMDE-SYS.

• 산업경영시스템학회지
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• 제37권4호
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• pp.12-23
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• 2014

The O&M (Operation and Maintenance) phase of offshore plants with a long life cycle requires heavy charges and more efforts than the construction phase, and the occurrence of an accident of an offshore plant causes catastrophic damage. So previous studies have focused on the development of advanced maintenance system to avoid unexpected failures. Nowadays due to the emerging ICTs (Information Communication Technologies) and sensor technologies, it is possible to gather the status data of equipment and send health monitoring data to administrator of an offshore plant in a real time way, which leads to having much concern on the condition based maintenance policy. In this study, we have reviewed previous studies associated with CBM (Condition-Based Maintenance) of offshore plants, and introduced an algorithm predicting the next failure time of the compressor which is one of essential mechanical devices in LNG FPSO (Liquefied Natural Gas Floating Production Storage and Offloading vessel). To develop the algorithm, continuous time Markov model is applied based on gathered vibration data.

• 한국인터넷방송통신학회논문지
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• 제15권6호
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• pp.209-215
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• 2015

반도체 관련 산업의 발전에 따라 반도체 제조공정에서 염산, 황산, 과산화수소, 불산, 피라니아 등과 같은 다양한 형태의 유독 가스와 화합물들이 사용되고 있고 누출 사고 역시 빈번하게 발생되고 있는 것이 사실이다. 유독 가스 누출사고 발생시 대량의 인명 피해가 발생되고 있는 것 역시 사실이다. 본 연구에서는 구미 불산 누출 사고와 같은 화학물질 누출 사고의 위험으로부터 인명을 보호하고 피해를 최소화 하기 위한 기본 해결책으로 대학에서의 MSDS 교육의 필요성에 대해 고찰하였다. 또한 GHS와 REACH 제도와 MSDS 이용의 적정성의 이해를 통해 유해 화학 물질의 노출로부터 안전을 지키는 문제에 대해 고찰하였다.

• 조명전기설비학회논문지
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• 제13권1호
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• pp.21-30
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• 1999

전력용 변압기의 절연 열화를 탐지하기 위한 연구가 오래 전부터 연구되어 왔으며 절연유에 함유된 연소성 가스분석 기술이 주로 활용되고 있다. 최근들어 고압 대용량화에따른 사고 파급효과가 커지게 되면서 on-line 탐지시스템의 필요성이 대두되면서 부분방전 신호 검출법이 연구되기 시작하였다. 본 연구는 부분방전 신호 검출법 중에서 탐촉자의 탈착이 용이한 초음파 신호 측정법에서 가장 큰 문제점인 잡음신호 분리를 위한 연구이다. 신호원의 개수와 위치를 측정할 수 있으므로 측정된 초음파 신호가 부분방전에 의한 것인지 외부 잡음인지를 구별할 수 있으며 변압기의 절연열화 판단에 한층 신뢰성을 향상시킬 수 있게 되었다.

• 한국안전학회지
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• 제31권3호
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• pp.156-161
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• 2016

An accident of an ammonia tank pipeline at a storage plant resulted in one death and three injuries in 2014. Many accidents including toxic gas releases and explosions occur in the freezing and refrigerating systems using ammonia. Especially, the consequence can be substantial due to that the large amount of ammonia is usually being used in the refrigeration systems. In this study, offsite consequence analysis has been investigated when ammonia leaks outdoors from large storages. Both flammable and toxic effects are under consideration to calculate the affected area using simulation programs for consequence analysis. ERPG-2 concentration (150 ppm) has been selected to calculate the evacuation distance out of various release scenarios for their dispersions in day or night. For offsite residential, the impact area by flammability is much smaller than that by toxicity. The methodology consists of two steps as followings; 1. Calculation for discharge rates of accidental release scenarios. 2. Dispersion simulation using the discharge rate for different conditions. This proactive prediction for accidental releases of ammonia would help emergency teams act as quick as they can.

• Nuclear Engineering and Technology
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• 제30권2호
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• pp.112-127
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• 1998

The present study is to assess the applicability of the best-estimate thermal-hydraulic codes, RELAP5/MOD3.2 and CATHARE2V1.3U, to the analysis of thermal-hydraulic behavior in PWRs during midloop operation following the loss of RHRS. The codes simulate an integral test, BETHSY 6.94, which was conducted in the large scale test facility of BETHSY in France. The test represents the accident where the loss of RHRS occurs during midloop operation with the pressurizer and upper head vents open and the sight level indicator broken. Besides, the hot legs are half filled with water and the upper parts of the primary cooling system are filled with nitrogen, with a letdown line open and only one SG available. The purposes of this study are to understand the physical phenomena associated with reflux cooling in the 5G U-tubes when noncondensable gas is present under low pressure and to assess the applicability of the codes to simulate the loss of RHRS event by comparing the predictions with the test results. The results of the study may contribute to actual applications for plant safety evaluation and description of the emergency operating procedure.

• Nuclear Engineering and Technology
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• 제53권12호
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• pp.4052-4059
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• 2021

The microstructure of the fuel pellet plays an essential role in fission gas buildup and release and is critical for the safe and continued operation of nuclear power stations. Structural analysis of uranium dioxide (UO₂)-molybdenum (Mo) composite fuel pellets prepared at a range of sintering temperatures from 1300 to 1800 ℃ was performed. Mo micro and nanoparticles were used in making the composite pellets. A systematic investigation into the influence of processing parameters during Spark Plasma Sintering (SPS) of the pellets on the microstructure, texture, grain size, and grain boundary characters of UO₂-Mo is presented. UO₂-Mo composite show significant differences in the fraction of general boundaries and also special/coincident site lattice (CSL) boundaries. EBSD orientation maps demonstrated that <111> texturing was observed in the pellets fabricated at 1500 ℃. The experimental investigations suggest that UO₂-Mo composite pellets have favorable microstructural features compared to the UO₂ pellet.

• 한국전기전자재료학회논문지
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• 제32권3호
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• pp.256-261
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• 2019

The use of military lithium batteries in this field accelerates the generation of internal pressure because the active materials, lithium and the electrolyte, react to form sulfur dioxide gas. This also reduces the amount of electrolyte. In this condition, batteries can 'vent' or 'explode' especially when completely discharged. Such venting and explosion can be regarded as a safety accident, as toxic gases and shrapnel are ejected from the batteries which can harm the user. A DTaQ was carried out in 2017 as a quality problem solution project to solve this safety issue. A protection circuit was thereby developed, which included a micro controller unit (MCU) which can stop battery usage when in an over-discharging state by sensing its low-voltage condition. In 2018, this concept was expanded to lithium batteries for the remote controlled ammunition system. This paper reports results of the improved performance.