• Journal of the Korean Society of Safety
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• v.38 no.5
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• pp.15-26
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• 2023

The relationship between the knowledge, attitude, and practice of the person in charge of designating a Class III facility was analyzed to improve its practice. As a field of knowledge, system knowledge and technical knowledge were considered, and attitudes were divided into cognitive, affective, and behavioral attitudes. A knowledge, attitude, and practice (KAP) survey was conducted, and the relationship among them was analyzed through correlation and regression analyses. The factors affecting the level of practice in designating the Class III facility were technical knowledge in the field of knowledge and cognitive and behavioral attitudes in the field of attitudes. Cognitive and behavioral attitudes were the two factors that most influenced the practice of designating a Class III facility. It is thought that the higher the level of cognitive and behavioral attitudes, the greater the ability to practice designating the Class III facility. The general characteristics of respondents influencing cognitive and behavioral attitudes were analyzed by safety inspection.

• Nuclear Engineering and Technology
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• v.39 no.4
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• pp.287-298
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• 2007

As part of the $AP1000^{TM}$ pressurized water reactor design certification program, a series of integral systems tests of the nuclear steam supply system was performed at the APEX-1000 test facility at Oregon State University. These tests provided data necessary to validate Westinghouse safety analysis computer codes for AP1000 applications. In addition, the tests provided the opportunity to investigate the thermal-hydraulic phenomena expected to be important in AP1000 small-break loss of coolant accidents (SBLOCAs). The APEX-1000 facility is a 1/4-scale pressure and 1/4-scale height simulation of the AP1000 nuclear steam supply system and passive safety features. A series of eleven tests was performed in the APEX-1000 facility as part of a U.S. Department of Energy contract. In all, four SBLOCA tests representing a spectrum of break sizes and locations were simulated along with tests to study specific phenomena of interest. The focus of this paper is the SBLOCA tests. The key thermal-hydraulic phenomena simulated in the APEX-1000 tests, and the performance and interactions of the passive safety-related systems that can be investigated through the APEX-1000 facility, are emphasized. The APEX-1000 tests demonstrate that the AP1000 passive safety-related systems successfully combine to provide a continuous removal of core decay heat and the reactor core remains covered with considerable margin for all small-break LOCA events.

• Nuclear Engineering and Technology
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• v.53 no.3
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• pp.776-792
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• 2021

Conventional integral effect test facilities were constructed to enable the precise observation of thermal-hydraulic phenomena and reactor behaviors under postulated accident conditions to prove reactor safety. Although these facilities improved the understanding of thermal-hydraulic phenomena and reactor safety, applications of new technologies and their performance tests have been limited owing to the cost and large scale of the facilities. Various nuclear technologies converging 4th industrial revolution technologies such as artificial intelligence, drone, and 3D printing, are being developed to improve plant management strategies. Additionally, new conceptual passive safety systems are being developed to enhance reactor safety. A new integral effect test facility having a noticeable scaling ratio, i.e., the (UNIST reactor innovation loop (URI-LO), is designed and constructed to improve the technical quality of these technologies by performance and feasibility tests. In particular, the URI-LO, which is constructed using a transparent material, enables better visualization and provides physical insights on multidimensional phenomena inside the reactor system. The facility design based on three-level approach is qualitatively validated with preliminary analyses, and its functionality as a test facility is confirmed through a series of experiments. The design feature, design validation, functionality test, and future utilization of the URI-LO are introduced.

• Nuclear Engineering and Technology
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• v.53 no.3
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• pp.793-803
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• 2021

The small PWR has been paid more and more attention due to its diversity of application and flexibility in the site selection. However, the large core power density, the small containment space and the rapid accident progress characteristics make it difficult to control the containment pressure like the traditional PWR during the LOCA. The pressure suppression system has been used by the BWR since the early design, which is a suitable technique that can be applied to the small PWR. Since the configuration and operating conditions are different from the BWR, the pressure suppression system should be redesigned for the small PWR. Conducting the experiments on the scale down test facility is a good choice to reproduce the prototypical phenomena in the test facility, which is both economical and reasonable. A systematic scaling method referring to the H2TS method was proposed to determine the geometrical and thermohydraulic parameters of the pressure suppression containment response test facility for the small PWR conceptual design. The containment and the pressure suppression system related thermohydraulic phenomena were analyzed with top-down and bottom-up scaling methods. A set of the scaling criteria were obtained, through which the main parameters of the test facility can be determined.

• Journal of the Korea Safety Management & Science
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• v.18 no.3
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• pp.91-97
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• 2016

Currently many geriatric hospitals have been built in Korea because younger people don't want to care their parents and have been decreasing for labor. However, the increasing geriatric hospitals make the increasing fire safety accidents. Therefore, this study is conducted by survey and face-to-face talk for analyzing fire safety problem of twelve among 15 geriatric hospitals in the north of Chung-Buk area. The result of this study is that infection and fall accident are higher than others and fire safety implement rate of safety rule followed by CEO is 71%. Monthly safety training rate is 49% and initial fire safety training not conducted is 33%. Yearly outside fire safety training rate is 97% but workers who know how to use fire evacuation facility are 61%. Furthermore, safety instruction rate of fire safety manager is much higher than supervisor's safety instruction. The cause of accident is facility (33%). In conclusion, the institution and rule improvement need for decreasing infection and falling, increasing implement level of fire safety rule and fire safety training, participation rate of supervisor for fire safety, quality of fire safety training, and investment of fire safety facility.

• Journal of the Korean Society of Safety
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• v.30 no.2
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• pp.14-20
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• 2015

The content of hazardous heavy metal of materials used in playground facility for children was investigated using X-ray fluorescence (XRF) and inductively coupled plasma (ICP) analyses, In order to examine the content of hazardous heavy metals according to the material color, four colors, i.e., green, red, yellow and blue, were categorized on the materials used. The highest lead content is observed in the yellow plastic samples. The yellow samples with relatively high lead content show that the chrome content is also high. This can explained that lead chromate, so-called chromium yellow, is normally used as a main pigment to express the yellow color. Therefore, it is concluded that hazardous heavy metal detected in the materials of playground facility for children is due to the pigments used for coloring. Based on above findings, the relationship between the color of materials used in playground facility for children and the content of hazardous heavy metal is discussed.

• Nuclear Engineering and Technology
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• v.55 no.2
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• pp.792-799
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• 2023

Non-reactor nuclear facilities are increasing remarkably in Korea combined with advanced technologies such as life and space engineering, and the diversification of the nuclear industry. However, the absence of a basic classification guideline related to the design of non-reactor nuclear facilities has created confusion whenever related projects are carried out. In this paper, related domestic and international technical guidelines are reviewed to present the classification criteria of non-reactor nuclear facilities in Korea. Based on these criteria, the classification of structures, systems and components (SSCs) for safety controls is presented. Using the presented classification criteria, classification of a hot cell facility, a representative non-reactor nuclear facility, was performed. As a result of the classification, the hot cell facility is classified as the hazard category 3, accordingly, the safety class was classified as non-nuclear safety, the seismic category as non-seismic (RW-IIb), and the quality class as manufacturers' standards (S).

• The Journal of the Convergence on Culture Technology
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• v.1 no.3
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• pp.69-75
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• 2015

In recent society, great and small accidents have happened frequently, so the demands for safety have increased. As numerical increase of tourists who use the amusement facilities, many accidents owing to amusement facility has arisen. The goal of this study is that suggests the improvement plans for the safety management system of amusement facilities. In order to achieve the goal of study, legislations, industrial scale, accident situation, and others relating to amusement facility business were considered in a lot of ways. From a series of study results, improvement plans are suggested for safety inspection, accident compensation insurance, accident investigation, and others relating to amusement facility business.

• Safety and Health at Work
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• v.12 no.3
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• pp.416-420
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• 2021

Hazardous area classification design is required to reduce the explosion risk in process plants. Among the international design guidelines, only IEC 60079-10-1 proposes a new type of zone, namely zone 2 NE, to prevent explosion hazards. We studied how to meet the zone 2 NE grade for a facility handling hydrogen gas, which is considered as most dangerous among explosive gases. Zone 2 NE can be achieved considering the grade of release, as well as the availability and effectiveness of ventilation, which are factors indicative of the facility condition and its surroundings. In the present study, we demonstrate that zone 2 NE can be achieved when the degree of ventilation is high by accessing temperature, pressure, and size of leak hole. The release characteristic can be derived by substituting the process condition of the hydrogen gas facility. The equations are summarized considering relation of the operating temperature, operating pressure, and size of leak hole. Through this relationship, the non-hazardous condition can be realized from the perspective of inherent safety by the combination of each parameter before the initial design of the hydrogen gas facility.

• Proceedings of the KIEE Conference
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• 2007.07a
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• pp.2072-2073
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• 2007

This paper describes the analysis of potential distribution and leakage current magnitude around the electrical fittings submerged in an underground shopping street. In the experiment, a couple of electrical utilities(outlet, fluorescent lamp) were submerged in a concrete water bath. The experimental results are expected to be utilized for the risk assessment and the safety countermeasure against the electric shock.