• Proceedings of the Korea Concrete Institute Conference
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• 2006.11a
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• pp.421-424
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• 2006

This study, in order for perceiving the mechanical attribute followed by the explosive spalling of high strength concrete material under high temperature and evaluating capacity of endurance of material, targets understanding capacity of endurance of material such as explosive spalling in high temperature, temperature by thickness of clothing, transformation extent, transformation speed and displacement, stocking the maximum load based on the Allowable Stress Design Method. As a result of experimenting the explosive spalling attribute of high strength concrete material, the one possibly causing serious damage is the 50 MPa concrete. In all aspects of 60 MPa concrete, explosive spalling happens. Especially, it is hazardous enough to reveal all the iron bar. All explosive spalling is intensively concentrated on the surface of concrete for the first $5{\sim}25$ minutes, which urges for the explosive spalling protection action. As a result of evaluating the structural safety by the transformation of high strength concrete, while beam assures the fire safety meeting regulation, 60 MPa shows the dramatic increase of transformation, which only counts 84% of safety. In a column, both the concrete exclusion and excessive explosive spalling are concentrated upper part of column, which brings about the dramatic transformation, so it only meets the 50% of safety regulation. Likewise, in 80, 100 MPa concrete which was never experimented considering the condition of domestic structural endurance stocking devices, the faster collapse is expected.

• Proceedings of the Korean Institute of Navigation and Port Research Conference
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• 1997.04a
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• pp.5-16
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• 1997

This paper presented a method of evaluting navigational safety of a ship by means of the integrated seakeeping performance index(ISPI). The ISPI is defined by measuring only any one factor through the medium of relative dangerousness of the other factors for evaluating seakeeping performance. This evaluation method can be applied to the ships for any types and loading conditions. In developing the practical evaluation system of navigational safety. it is expected to be useful for developing the optimum type of ship by applying at the initial design phase.

• Journal of Navigation and Port Research
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• v.38 no.6
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• pp.689-694
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• 2014

The Korean government has introduced and enforced maritime traffic safety assessment to secure traffic safety since 2010. The maritime traffic safety assessment is needed by law to design a new port or modify an existing one. According to Korea Maritime Safety Act, in the assessment the propriety of marine traffic system consists of the safety of channel transit and berthing/unberthing maneuver, safety of mooring, and safety of marine traffic flow. The safety of channel transit and berthing/unberthing maneuver can be evaluated only by ship-handling simulation. The ship-handling simulation is carried out by sea pilots working with the port concerned. The vessel's proximity measure is an important factor to evaluate traffic safety. The proximity measure is composed of vessel's closest distance to channel boundary and probability of grounding/collision. What is more, the probability of grounding becomes important. According to central limit theorem, a sample has a normal distribution on condition that its size is more than 30. However, more than 30 simulation runs bring about the increase of assessment period and difficulty of employing sea pilots. Therefore this paper is to find out minimum sample size for evaluating vessel's proximity. First sample sets of size of 3, 5, 7, 9 etc. are selected randomly on the basis of normal distribution. And then KS test for goodness of fit and t-test for confidence interval are applied to each sample set. Finally this paper decides the minimum sample size. As a result this paper suggests the minimum sample size of 5, that is, the simulation of more than five times.

• Journal of Platform Technology
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• v.11 no.6
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• pp.47-55
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• 2023

With the goal of ensuring the safety of wheelchair users, this study was conducted using finite element analysis, focusing on the development of a platform that can be used to evaluate safety during the design stage. Safety evaluation criteria for wheelchairs used in vehicles are defined in ANSI/RESNA WC19 and ISO 7176-19. Based on these standards, finite element analysis was performed to assess the sectional forces of each component of the wheelchair and sensitivity analysis was conducted based on the specifications. These results were used to derive equivalent composite loads for the wheelchair's main components, determine the necessary sectional specifications for these main components in the wheelchair design phase, and investigate the process of safety assessment verification. The study showed that member forces vary with changes in the cross-sectional values of the wheelchair frame's main components, with the front and rear lower members, as well as the rear upper and lower members, requiring the highest cross-sectional values for safety design. This study offers a proactive method for evaluating safety in the wheelchair design stage, and in future research, we plan to develop a safety evaluation platform based on these results.

• Proceedings of the KIEE Conference
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• 1993.07a
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• pp.140-143
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• 1993

Station Blackout(SBO) event means the complete loss of alternating current(AC) electrical power to the essential & nonessential switchgear buses in a nuclear power plants. Since many safety systems in nuclear power plants depend upon alternative current power, the SBO event could be an important contributor to damage of reactor core. Therefore, the SBO events have been considered as a very important safety issues in a nuclear power plants. In this paper, as evaluating the design characteristics of offsite & emergency power systems, an acceptable minimum SBO duration is calculated. And it is presented that the design method for alternative AC(AAC) sources to cope with the SBO events.

• Transactions of the Korean Society of Pressure Vessels and Piping
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• v.8 no.1
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• pp.25-32
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• 2012

Korea Hydro & Nuclear Power Co. (KHNP) has developed and implemented the maintenance effectiveness monitoring (MR) programs for the operating nuclear power plants. The MR program is developed by reflecting design characteristics of the operating nuclear power plants to monitor the plant performance for improving the safety and reliability. Recently, KHNP has built a new nuclear power plant, and developed the MR program to establish the advanced maintenance system by reflecting unique design characteristics based on the OPR1000 standard model. So, the MR program developed in this study has another characteristics in comparison with the OPR1000 standard model, and we will verify the suitability of the MR program through evaluating initial performance of the plant. The safety and reliability of the new plant will be improved by developing and implementing the MR program.

• Proceeding of Spring/Autumn Annual Conference of KHA
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• 2009.04a
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• pp.273-277
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• 2009

This study was conducted to develop standards for evaluating what extant the physical environments of housing which can cope with the needs of the aging society. This study was consisted through literature investigation research mainly, and research target literature limits keyword to elderly housing environment and chose connected domestic various literatures. The scope of evaluation was limited to the indoor spaces and outdoor spaces of housing as it was thought that the elderly spend much more time at indoor, outdoors, considering their physical characteristics. The study are as follows ; First, in outdoor only area from design environment element accessibility, and safety emphasized from equipment element, health of community territory was expose from design environment element that supportiveness is emphasized from equipment element. Second, in living room safety emphasized from design environment element in bedroom and bathroom of indoor individuation space, vestibule, balcony supportiveness, health was expose that is emphasized kitchen and mess. Also, was expose that supportiveness is emphasized from equipment element of all individuation spaces. Third, was expose that design environment element in corridor that is indoor official business space, stair, lobby, elevator and safety from equipment element and supportiveness are emphasized.

• Journal of the Korean housing association
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• v.21 no.1
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• pp.151-159
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• 2010

This study was conducted to develop standards for evaluating what extant the physical environments of housing which can cope with the needs of the aging society. This study was consisted through literature investigation research mainly, and research target literature limits keyword to elderly housing environment and chose connected domestic various literatures. The study are as follows; First, in outdoor only area from design environment element accessibility, and safety emphasized from equipment element, health of community territory was expose from design'environment element that supportiveness is emphasized from equipment element. Second, in living room safety emphasized from design' environment element in bedroom and bathroom of indoor individuation space, vestibule, balcony supportiveness, health was expose that is emphasized kitchen and mess. Also, was expose that supportiveness is emphasized from equipment element of all individuation spaces. Third, was expose that design environment element in corridor that is indoor official business space, stair, lobby, elevator and safety from equipment element and supportiveness are emphasized.

• Journal of Navigation and Port Research
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• v.30 no.2
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• pp.125-130
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• 2006

Waves, which are the main source of ship motions in a seaway, considerably affect the performance of a ship. The study of waves and their impact on ship motions within harbors is an important aspect of the design and operation of harbors. The prediction of incoming groups of waves is particularly important for evaluating ship motion within a harbor. Such a prediction makes it possible to evaluate ship safety more accurately. The wave transformation model reported here is applied to actual ports based on Boussinesq wave equations both non-linear and dispersive wave processes be considered in order to capture physical effects such as wave shoaling, refractions, reflection and diffraction in variable depth environments. The prediction of incoming groups of waves is particularly important for evaluating ship motion within a harbor, Such a prediction makes it possible to evaluate ship safety more accurately and provide safe wave informations for navigation. Furthermore, a wave information support system is proposed for entering ships as one technique for improving the safety of ship operations. This system predicts the run of waves and reduces the danger by identifying the most dangerous point near the harbor entrance at the small wave groups.

• Journal of the Earthquake Engineering Society of Korea
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• v.22 no.3
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• pp.113-119
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• 2018

The probabilistic seismic safety assessment is one of the methodology to evaluate the seismic safety of the nuclear power plants. The site characteristics of the nuclear power plant should be reflected when evaluating the seismic safety of the nuclear power plant. The Korea seismic characteristics are strong in high frequency region and may be different from NRC Regulatory Guide 1.60, which is the design spectrum of nuclear power plants. In this study, seismic response of a nuclear power plant structure by Pohang earthquake (2017.11.15. (KST)) is investigated. The Pohang earthquake measured at the Cheongsong seismic observation station (CHS) is scaled to the peak ground acceleration (PGA) of 0.2 g and the seismic acceleration time history curve corresponding to the design spectrum is created. A nuclear power plant of the containment building and the auxiliary buildings are modeled using OPENSEES to analyze the seismic response of the Pohang earthquake. The seismic behavior of the nuclear power plant due to the Pohang earthquake is investigated. And the seismic performances of the equipment of a nuclear power plant are evaluated by the HCLPF. As a result, the seismic safety evaluation of nuclear power plants should be evaluated based on site-specific characteristics of nuclear power plants.