• Korean Institute of Interior Design Journal
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• v.24 no.6
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• pp.202-211
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• 2015

This study attempts to deduce the necessity and validity of complexation, and suggests complexation through complexation suitability evaluations as follows. First, the concept and current state of leisure facilities for the elderly and elementary facilities and architectural complexation were investigated through theoretical considerations. Second, the target schools for complexation of 'elementary school-leisure facility for the elderly' were selected. The aspects of facility introduction of an elementary school, teacher support facility, convenience facility for the disabled, safety and security facilities as well as school facility accessibility were investigated on the basis of the data attained from theoretical considerations. Third, the feasibility of complexation of leisure facilities for the elderly was reviewed, based on the investigated data on complexation-targeted elementary school. Regarding school building and support facilities, with a focus on leisure programs for the elderly, the availability and number of rooms, extra numbers of regular classrooms and the room condition were assessed on the basis of the analysis of operational perspective of each facility. The convenience facilities for the disabled were examined by classifying them into interventional facility in consideration of facilities for the elderly, pursuant to the provisions in the convenience promotion assurance act for the disabled, elderly and pregnant women. Safety and security facilities were evaluated in an effort to assess the safety issue of the elderly and children. The result of the evaluation of the 6 elementary schools in Seong-buk county based on the above-mentioned four measurement standards shows that they scored 107~124 points out of the total 155 points, with the average of 118.5 points. This is more than the medium score and shows the possible complexation of the elementary school facilities as the leisure facilities for the elderly, and at the same time it may lead each school to find out the elements conducive to enhancing the complexation as a result of the evaluation. Through the evaluation data, I expect that we contribute to promoting the process of the evaluation of the appropriateness of complexation and the efficient complexation.

• Proceedings of the KSR Conference
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• 2008.06a
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• pp.919-922
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• 2008

The objective of this study is to design the full-scale fire test facility of the railroad vehicle with CFD simulation. In the results, the step expansion system should be good enough for the measuring system. Uniform flow is achieved at eight-to-ten diameters of the expanded duct behind the step for moderate expansion ratios($D_{orifice}/D_{duct}$ = 2 being a good choice). To optimization of the fire products collector system with 5 dampers, the additional CFD simulation was also carried out. These results will be help for the railroad fire safety research.

• The Journal of Sustainable Design and Educational Environment Research
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• v.17 no.2
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• pp.11-21
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• 2018

This study suggests desirable disaster safety education curriculum through analyzing the operational status of the school disaster safety management training course and demand survey of school staff. First, the problem of the disaster safety training course of the school is not connected with the lack of law and system and the school disaster safety job. Second, improvement of law and system and variety of training should be made to acquire professional knowledge. Third, it is necessary to divide curriculum into the following four categories, according to educational needs of public officials ; Educational administration officers course focused on facility safety, maintenance and disaster countermeasure. Educational officials in technical post course addressing approval and permission of school facility projects, seismic reinforcement of school building, etc. Educational supervisors course covering roles and responsibilities of the school safety supervisors in the event of disaster. Teaching staffs course focused on safety instructions for students. Fourth, it is found that lectures and experiential learning methods are the most desirable methods of teaching and learning, and the major ranks are earthquake disaster, fire, gas, typhoon, school road, and electrical safety.

• Nuclear Engineering and Technology
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• v.53 no.4
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• pp.1345-1356
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• 2021

Damage to nuclear power plants causes human casualties and environmental disasters. There are electrical facilities that control safety-related devices in nuclear power plants, and seismic performance is required for them. The 2016 Gyeongju earthquake had many high-frequency components. Therefore, there is a high possibility that an earthquake involving many high frequency components will occur in South Korea. As such, it is necessary to examine the safety of nuclear power plants against an earthquake with many high-frequency components. In this study, the shaking table test of electrical facilities was conducted against the design earthquake for nuclear power plants with a large low-frequency components and an earthquake with a large high-frequency components. The response characteristics of the earthquake with a large high-frequency components were identified by deriving the amplification factors of the response through the shaking table test. In addition, safety of electrical facility against the two aforementioned types of earthquakes with different seismic characteristics was confirmed through limit-state seismic tests. The electrical facility that was performed to the shaking table test in this study was a motor control center (MCC).

• Nuclear Engineering and Technology
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• v.45 no.5
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• pp.695-700
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• 2013

Thirty-eight radiation safety reports for brachytherapy equipment were evaluated to determine the current status of brachytherapy units in Korea and to assess how radiation oncology departments in Korea complete radiation safety reports. The following data was collected: radiation safety report publication year, brachytherapy unit manufacturer, type and activity of the source that was used, affiliation of the drafter, exposure rate constant, the treatment time used to calculate workload and the HVL values used to calculate shielding design goal values. A significant number of the reports (47.4%) included the personal information of the drafter. The treatment time estimates varied widely from 12 to 2,400 min/week. There was acceptable variation in the exposure rate constant values (ranging between 0.469 and 0.592 ($R{\cdot}m^2/Ci{\cdot}hr$), as well as in the HVLs of concrete, steel and lead for Iridium-192 sources that were used to calculate shielding design goal values. There is a need for standard guidelines for completing radiation safety reports that realistically reflect the current clinical situation of radiation oncology departments in Korea. The present study may be useful for formulating these guidelines.

• Nuclear Engineering and Technology
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• v.50 no.3
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• pp.356-367
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• 2018

A series of tests dedicated to station blackout (SBO) accident scenarios have been recently performed at the $Prim{\ddot{a}}rkreislauf-Versuchsanlage$ (primary coolant loop test facility; PKL) facility in the framework of the OECD/NEA PKL-3 project. These investigations address current safety issues related to beyond design basis accident transients with significant core heat up. This work presents a detailed analysis using the best estimate thermal-hydraulic code TRACE (v5.0 Patch4) of different SBO scenarios conducted at the PKL facility; failures of high- and low-pressure safety injection systems together with steam generator (SG) feedwater supply are considered, thus calling for adequate accident management actions and timely implementation of alternative emergency cooling procedures to prevent core meltdown. The presented analysis evaluates the capability of the applied TRACE model of the PKL facility to correctly capture the sequences of events in the different SBO scenarios, namely the SBO tests H2.1, H2.2 run 1 and H2.2 run 2, including symmetric or asymmetric secondary side depressurization, primary side depressurization, accumulator (ACC) injection in the cold legs and secondary side feeding with mobile pump and/or primary side emergency core coolant injection from the fuel pool cooling pump. This study is focused specifically on the prediction of the core exit temperature, which drives the execution of the most relevant accident management actions. This work presents, in particular, the key improvements made to the TRACE model that helped to improve the code predictions, including the modeling of dynamical heat losses, the nodalization of SGs' heat exchanger tubes and the ACCs. Another relevant aspect of this work is to evaluate how well the model simulations of the three different scenarios qualitatively and quantitatively capture the trends and results exhibited by the actual experiments. For instance, how the number of SGs considered for secondary side depressurization affects the heat transfer from primary side; how the discharge capacity of the pressurizer relief valve affects the dynamics of the transient; how ACC initial pressure and nitrogen release affect the grace time between ACC injection and subsequent core heat up; and how well the alternative feeding modes of the secondary and/or primary side with mobile injection pumps affect core quenching and ensure stable long-term core cooling under controlled boiling conditions.

• Journal of the Korea Institute of Building Construction
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• v.20 no.3
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• pp.279-287
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• 2020

Recently, the demand for underground-type ammunition storage facilities has increased. Comparing with a ground-type ammunition storage facility, the underground-type ammunition storage facility can decrease the standard of safety distance because fragment and blast wave can be locked in the rock formation. However, the absence of a design method on the underground-type ammunition storage chamber became a major setback for the construction promotion. In this study, the process for designing an overall configuration of the underground-type ammunition storage facility was provided. First, the determination method for configuration and number of the chamber was developed by performing the ammunition storage simulation. Then, a tunnel (i.e., transfer channel for vehicles) and designed chambers can be arranged on the basis of safety distance standard. The safety distance standard also should be considered for determining the location and the size of entrances because of the blast wave and fragment effect at the entrances when an explosion is generated inside a chamber. In addition, considerations on the design for the waterproof and the drainage of subsurface water were analyzed through construction cases. Finally, an example of designing underground-type ammunition storage chambers was provided in order to verify the developed design process.

• Proceedings of the SAREK Conference
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• 2008.06a
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• pp.552-557
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• 2008

This paper introduces to schematic design for Korea Institute of Toxicology Second Campus at Jeong-eup and provides fundamental information and data in order to design this laboratory facility to meet the criteria of G.L.P(Good Laboratory Practice), AAALAC(Association for Assessment and Accreditation of Laboratory Animal Care) and so on. This paper especially focus on design criteria, HVAC(Heating Ventilating and Air Conditioning) equipment and systems, plumbing equipment and systems, maintenance of equipment and systems and energy saving system of this laboratory facility.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.6 no.4
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• pp.357-368
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• 2008

On July 31, 2008, the Government issued the construction and operation permit for the first low and intermediate level radioactive waste disposal facility in the Republic of Korea. In this paper, the fundamental regulatory framework, regulatory requirements and technical standards of the disposal facility are introduced, and the phased review process adopted for evaluation of the safety of the facility is briefly described. The Atomic Energy Act sets forth a stepwise regulatory framework for the whole life-cycle of the disposal facility such as siting, design, construction, operation, closure and institutional control. More detailed regulatory requirements and technical standards are stipulated in the subsequent regulations of the Atomic Energy Act and a series of Notices issued by the Ministry of Eduction, Science and Technology. The Korea Institute of Nuclear Safety, as entrusted by the Ministry under the Atomic Energy Act, conducted safety review on the disposal facility, and evaluated the compliance with relevant criteria in all technical elements(i.e. siting and structural safety, radiological environmental impact, operational safety, systems and components, quality assurance, and total systematic performance assessment, etc.). The overall safety review process can be phased into inception phase, initial review phase, main review phase and completion phase. The review results were reported to and deliberated by the five Sub-committees of the Special Committee on Nuclear Safety, and then reported to the Ministry. The Ministry issued the construction and operation permit of the disposal facility through the deliberation of the review results by the Nuclear Safety Commission. Hereafter, the safety of the repository will be reassured by a series of subsequent regulatory inspections and reviews under the Atomic Energy Act. In addition, the licensee's continuous implementation of the "Safety Promotion Plan" may also enhance the long-term safety of the repository and contribute to build-up the confidence of the safety case.

• Journal of The Korea Institute of Healthcare Architecture
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• v.11 no.2
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• pp.45-54
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• 2005

The purpose of this paper is to analyze the handicapped facility in residential outside area, to found how to improve the law in analyzing the residential area and to suggest consideration factor in design phase. To concentrate the study, the objects of case study are selected carefully, also case study method is selected as well as objects. After observing the summary of objects, the checklist is made accordance with the improvement law of facility. The checklist has the general and detail factor about outdoor residential area, and the detail factor is based on the improvement law of facility and is used to examine and analyze.