• Korean Institute of Interior Design Journal
• /
• v.19 no.6
• /
• pp.224-232
• /
• 2010

This paper aims to identify the characteristics and the current situation of the architectural characteristics, children's characters using facilities, and status of management and utilization by surveying 'Day Service for Children' in Tokyo-do. First, About the status of management and utilization, 'Day Service for Children' is operated by a local government, NPO corporate group and social welfare corporate. There are not big differences of the care program or running hours depending on operating principals but there are differences depending on staff organization, number of children and space constitution. Also, infants ratio at 'Day Service for Children' is high for the purpose of detecting disability early and supporting their development early. They have diverse disabilities but developmental disabilities' ratios high and most children are using both this facility and normal nursery centers together. Samples for proper child care based on status of space constitutions were installing lock, raising door knobs and using softer floor materials which are for children's safety. For the problem of space utilization, most comments were about lack of space which is not enough for teaching and training materials. Therefore, as an example, observation rooms for parents and teachers were sometimes used as storages and it changes teachers' moving direction, staying area and behavior zone. The programs of 'Day Service for Children' are divided to group teaching and private one. It will be the best if they have separate spaces such as group class room, private class room and play room. When they were operated by NPO corporate group or Social welfare corporate, there are many cases that their space was not properly zoned for each activity.

• Journal of Information Technology Services
• /
• v.19 no.5
• /
• pp.33-47
• /
• 2020

In recent years, due to the demand for operating efficiency and cost reduction of industrial facilities, remote access via the Internet is expanding. the control network accelerates from network separation to network connection due to the development of IIoT (Industrial Internet of Things) technology. Transition of control network is a new opportunity, but concerns about cybersecurity are also growing. Therefore, manufacturers must reflect security compliance and standards in consideration of the Internet connection environment, and enterprises must newly recognize the connection area of the control network as a security management target. In this study, the core target of the control system security threat is defined as the network boundary, and issues regarding the security architecture configuration for the boundary and the role & responsibility of the working organization are covered. Enterprises do not integrate the design organization with the operation organization after go-live, and are not consistently reflecting security considerations from design to operation. At this point, the expansion of the control network is a big transition that calls for the establishment of a responsible organization and reinforcement of the role of the network boundary area where there is a concern about lack of management. Thus, through the organization of the facility network and the analysis of the roles between each organization, an static perspective and difference in perception were derived. In addition, standards and guidelines required for reinforcing network boundary security were studied to address essential operational standards that required the Internet connection of the control network. This study will help establish a network boundary management system that should be considered at the enterprise level in the future.

• Nuclear Engineering and Technology
• /
• v.46 no.3
• /
• pp.313-342
• /
• 2014

A Nuclear Energy Agency (NEA), Organization for Economic Co-operation and Development (OECD) benchmark for Uncertainty Analysis in Modeling (UAM) is defined in order to facilitate the development and validation of available uncertainty analysis and sensitivity analysis methods for best-estimate Light water Reactor (LWR) design and safety calculations. The benchmark has been named the OECD/NEA UAM-LWR benchmark, and has been divided into three phases each of which focuses on a different portion of the uncertainty propagation in LWR multi-physics and multi-scale analysis. Several different reactor cases are modeled at various phases of a reactor calculation. This paper discusses Phase I, known as the "Neutronics Phase", which is devoted mostly to the propagation of nuclear data (cross-section) uncertainty throughout steady-state stand-alone neutronics core calculations. Three reactor systems (for which design, operation and measured data are available) are rigorously studied in this benchmark: Peach Bottom Unit 2 BWR, Three Mile Island Unit 1 PWR, and VVER-1000 Kozloduy-6/Kalinin-3. Additional measured data is analyzed such as the KRITZ LEU criticality experiments and the SNEAK-7A and 7B experiments of the Karlsruhe Fast Critical Facility. Analyzed results include the top five neutron-nuclide reactions, which contribute the most to the prediction uncertainty in keff, as well as the uncertainty in key parameters of neutronics analysis such as microscopic and macroscopic cross-sections, six-group decay constants, assembly discontinuity factors, and axial and radial core power distributions. Conclusions are drawn regarding where further studies should be done to reduce uncertainties in key nuclide reaction uncertainties (i.e.: $^{238}U$ radiative capture and inelastic scattering (n, n') as well as the average number of neutrons released per fission event of $^{239}Pu$).

• The Journal of Sustainable Design and Educational Environment Research
• /
• v.22 no.1
• /
• pp.13-27
• /
• 2023

This study analyzed the reasons for extending the construction period considering factors such as the quality of construction materials, safety and cost-effectiveness of construction, size of construction, academic schedule, and local conditions (complaints) when determining the appropriate period for school construction projects tailored to a specific region or educational office. Based on the example of construction projects for school facility improvement by education office A, this study conducted a case study to identify the motives for construction period extension. To determine the appropriate construction period for school facilities, this study conducted a comprehensive review of construction projects under the jurisdiction of education office A, examined data from the Meteorological Data Open Portal, and performed advanced statistical analysis. Future case studies must determine the appropriate construction period for school facilities in a rational and systematics.

• Transactions of the Korean Society of Mechanical Engineers A
• /
• v.40 no.9
• /
• pp.775-782
• /
• 2016

In this study, elevated temperature design and integrity evaluation have been conducted using two different piping design codes for the high-temperature piping systems of sodium integral effect test loop for safety simulation and assessment(STELLA-2) being developed by KAERI(Korea Atomic Energy Research Institute). The design code of ASME B31.1 for power piping and French nuclear grade piping design guideline, RCC-MRx RD-3600 were applied, and conservatism of those codes was quantified based on the piping integrity evaluation results. The piping system of Model DHRS, Model IHTS and PSLS are to be installed in STELLA-2. The integrity evaluation results for the three piping systems according to the two design codes showed that integrity of the piping system was confirmed. As a code comparison result, ASME B31.1 was shown to be more conservative for sustained loads while RD-3600 was more conservative for thermal loads compared to B31.1.

• The Journal of The Korea Institute of Intelligent Transport Systems
• /
• v.21 no.6
• /
• pp.284-298
• /
• 2022

It is necessary to acquire information on traffic safety facilities installed on the roadways specifically for the operation of autonomous vehicles. The purpose of this study is to prepare a Korean version of an integrated message-set design as a way to provide to autonomous vehicles standardized information on traffic safety facilities. In this study, necessary facilities are classified according to four criteria (no legal basis; not providing information to autonomous vehicles; providing duplicate information; not standardized, and too difficult to generalize) based on information that must be provided to operate autonomous vehicles. The priority of information delivery (gross negligence followed by behavior change) was classified according to the importance of the information to be provided during autonomous driving, and the form was defined for the classification code in the information delivered. Finally, the information location and delivery method of traffic facilities for compliance with SAE J2735 were identified. This study is meaningful in that it provides a plan for roadway operations by suggesting a method for providing information to autonomously driven vehicles.

• Korean Journal of Construction Engineering and Management
• /
• v.25 no.5
• /
• pp.15-24
• /
• 2024

System support is a facility that is temporarily installed to support vertical loads at construction sites, and is assembled and installed by reused individual members. These characteristics are likely to lead to poor performance of installed system supports, and even though it is institutionalized to check structural safety at the their design phase, accidents continue to occur at the construction site. Accordingly, safety management of system support is implemented through various institutional methods, but the current system does not consider the performance degradation of temporary facilities due to the reuse of individual temporary members. Therefore, the purpose of this study is to verify the performance of assembled system support. In order to do achieve this purpose, the authors divided individual system supports into unused and used groups and performed compression performance test with defined models assembled with those two groups of system supports. The results of this study are expected to be meaningful as a research case that can quantitatively evaluate safety systems and standards for the performance of existing temporary facilities and suggest directions for improving the safety management system of temporary facilities in the future.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
• /
• v.17 no.4
• /
• pp.375-387
• /
• 2019

In this study, the radiation dose rates for the design basis fuel of 360 assemblies CANDU spent nuclear fuel transportation cask were evaluated, by measuring radiation source terms for the design basis fuel of a pressurized heavy water reactor. Additionally, radiological safety evaluation was carried out and the validity of the results was determined by radiological technical standards. To select the design basis fuel, which was the radiation source term for the spent fuel transportation cask, the design basis fuels from two spent fuel storage facilities were stored in a spent fuel transportation cask operating in Wolsung NPP. The design basis fuel for each transportation and storage system was based on the burnup of spent fuel, minimum cooling period, and time of transportation to the intermediate storage facility. A burnup of 7,800 MWD/MTU and a minimum cooling period of 6 years were set as the design basis fuel. The radiation source terms of the design basis fuel were evaluated using the ORIGEN-ARP computer module of SCALE computer code. The radiation shielding of the cask was evaluated using the MCNP6 computer code. In addition, the evaluation of the radiation dose rate outside the transport cask required by the technical standard was classified into normal and accident conditions. Thus, the maximum radiation dose rates calculated at the surface of the cask and at a point 2 m from the surface of the cask under normal transportation conditions were respectively 0.330 mSv·h^-1 and 0.065 mSv·h^-1. The maximum radiation dose rate 1 m from the surface of the cask under accident conditions was calculated as 0.321 mSv·h^-1. Thus, it was confirmed that the spent fuel cask of the large capacity heavy water reactor had secured the radiation safety.

• Journal of the Korean Institute of Landscape Architecture
• /
• v.45 no.4
• /
• pp.81-91
• /
• 2017

The purpose of this study is to establish a system of planning elements necessary for effective healing garden. We suggested new planning parts and elements for healing garden through analyzing prior literature and evaluated the importance of planning elements through expert surveys. The results of the study are stated as follows. First, we suggested five planning parts and 19 planning elements. $\LARGE{\cdot}$ Planning parts: Physical environment, social environment, cognitive environment, functional environment, psychological environment. $\LARGE{\cdot}$ Planning elements: Plant planting, garden view, hydroponic space, shade space, work space, recreation space, community space, exercise space, landmark element, sign system, safe facilities and materials, disaster safety facility, universal design, accessible path, economical maintenance, sight openness, privacy guaranteed, variety of resting space, artistic element. Second, as a result of analyzing the importance of planning elements, the first place was the planting, the second place was the safety facilities for the disaster, and the third was diversity of rest space. In addition, the artistic elements and the landmark elements were ranked 18th and 19th, respectively. Third, we evaluated the level of importance of planning elements and classified it into three groups. The most important A group included two elements(plant planting, disaster safety facility), the next important B group included eleven elements(variety of resting space, community space, hydroponic space, universal design, safe facilities and materials, economical maintenance, accessible path, privacy guaranteed, garden view, work space, sight openness) and the less important C group included six elements(shade space, exercise space, recreation space, sign system, artistic element, landmark element). We suggest that, in creating a healing garden, the two elements in A group are essential elements and the eleven elements in B group should be importantly applied. In addition, the six elements in C group are recognized as arbitrarily selectable elements due to the relatively low importance levels.

• Journal of Korean Tunnelling and Underground Space Association
• /
• v.23 no.6
• /
• pp.577-587
• /
• 2021

Room and Pillar method is an underground facility construction method that maximizes the strength of the in-situ ground. In order to secure the safety of the underground space, it is necessary to secure the safety of the room actually used in addition to the safety of pillar of the room and Pillar method. In this study, the evaluation method for the safety of the room and rock pillar in the room and pillar method was studied through numerical analysis. Numerical analysis was performed for a total of 125 cases using ground conditions, pillar width, and room width as parameters, and the results were derived. As for the safety factor of the pillar, it was confirmed that the safety factor increased when the strength of the ground increased, and it was confirmed that the increment in the safety factor decreased when the width of the pillar was widened. The room strain was evaluated by applying the Critical strain. As the width of the pillar became narrower, the Critical strain was higher, and as the width of the room became smaller, the Critical strain was smaller. As a result of the correlation analysis between the safety factor of the pillar and the room strain, it was possible to derive the upper limit of the room strain that can secure the standard safety factor of the pillar according to the width of the pillar. It is judged that the results derived from this study can be used as a guideline to secure the safety of the room when the actual design is performed in consideration of the ground conditions and room width.