• Nuclear Engineering and Technology
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• v.52 no.11
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• pp.2660-2666
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• 2020

Korea successfully achieved energy independence in the shortest period of time from being the poorest country in terms of energy 50 years ago through steady development of nuclear technology. In the past, the nuclear industry has been driven through government-centered policy development, public institution-based research, and industrial facility and infrastructure construction. Consequently, South Korea became a nuclear energy powerhouse exporting nuclear power plants to the UAE, surpassing the level of domestic technological independence. However, in recent years, the nuclear industry in Korea has experienced a decline in new plant construction since the Fukushima accident in Japan, which caused changes in public perspectives regarding nuclear power plant operation, more stringent safety standards on the operation of nuclear power plants, and a shift in governmental energy policy. These changes are expected to change the domestic nuclear industry ecosystem. Therefore, in this study, we investigate the priority of technology development investment from the perspective of experts in private nuclear power companies, shifting the focus from government-led nuclear R&D policies. To establish a direction in nuclear technology development, a survey was conducted by applying an analytic hierarchy analysis to experts who have worked in nuclear power plants for more than 15 years. The analysis items of focus were the 3 attributes of strategic importance, urgency, and business feasibility of four major fields related to nuclear energy: nuclear safety, decommissioning, radioactive waste management, and strengthening industrial competitiveness.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.21 no.4
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• pp.489-502
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• 2023

This article presents the crucial role played by the French underground research laboratory (URL) in initiating the deep geological repository project Cigéo. In January 2023, Andra finalized the license application for the initial construction of Cigéo. Depending on Government's decision, the construction of Cigéo may be authorized around 2027. Cigéo is the result of a National program, launched in 1991, aiming to safely manage high-level and intermediate level long-lived radioactive wastes. This National program is based on four principles: 1) excellent science and technical knowledge, 2) safety and security as primary goals for waste management, 3) high requirements for environment protection, 4) transparent and open-public exchanges preceding the democratic decisions and orientations by the Parliament. The research and development (R&D) activities carried out in the URL supported the design and the safety demonstration of the Cigéo project. Moreover, running the URL has provided an opportunity to gain practical experience with regard to the security of underground operations, assessment of environmental impacts, and involvement of the public in the preparation of decisions. The practices implemented have helped gradually build confidence in the Cigéo project.

• Journal of Korean Society of Disaster and Security
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• v.12 no.3
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• pp.59-67
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• 2019

In this study, the UAV (Unmammed Aerial Vehicle) was applied for the photogrammetry of the construction site and the safety management of steel pipe scaffold. The research site is a temporary facility for building reinforcement on Samcheok Campus of Kangwon National University. The installation condition of the steel pipe scaffold was investigated, and the pillar distance, the beam distance and the wale distance were surveyed. As a result, it was found that the beam distance of the scaffold in the longitudinal direction was in good agreement with the standard, but the pillar distance and the wale distance were found to be less than the standard. Three-dimensional data can be used in drone shooting to enable three-dimensional measurement, so that it is possible to measure facilities hidden or located inside other facilities. Through the drone shooting, the condition of the site can be quickly recorded and the surveying can be carried out without interfering with the work of the field personnel. Although the installation of the temporary structure must be strictly observed to ensure the safety of the workers, it is found that the installation standards are still neglected in the field. In order to prevent this practice, it was thought that the legal system should be supplemented so that it could be checked periodically by using UAV in the field process management.

• Nuclear Engineering and Technology
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• v.11 no.2
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• pp.127-132
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• 1979

A model is considered in order to evaluate the potential risk from a nuclear facility directly combining the on-site meteorological data. The model is utilized to evaluate the environmental consequences from the routine releases during normal plant operation as well as following postulated accidental releases. The doses to individual and risks to the population-at-large are also analyzed in conjunction with design of rad-waste management and safety systems. It is observed that the conventional analysis, which is done in two separate unaffiliated phases of releases and atmospheric dispersion tends to result in unnecessary over-design of the systems because of high resultant doses calculated by multiplication of two extreme values.

• Korean Journal of Human Ecology
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• v.13 no.5
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• pp.751-763
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• 2004

This study aims to identify children's after-school facilities in Cheonan, to evaluate their programs, and to further suggest desirable directions of those programs. During this study, we found that the facilities in Cheonan are much less in numbers and no better than we expected. Especially, it is shown that most of the study rooms there are evaluated as relatively the worst facilities in terms of space organization, health care and safety, daily schedule and management, and program evaluation process. In conclusion, this study proposes that such facilities should be greatly expanded and improved in the program development as well as in the working environment. We also propose to newly establish a regional center which supports and certifies educational programs of each after-school facility.

• Proceedings of the KIEE Conference
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• 2005.05a
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• pp.185-187
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• 2005

The reactor protection system is the most important function for the safe operation of nuclear powerplants (NPPs) in that such system protects a nuclear reactor tore whose damage can cause an enormous disaster to the nuclear facility and the public. A digital reactor protection system (DRPS) is being developed in KAERI for use in the newly-constructed NPPs and also for replacing the existing analog-type reactor Protection systems. In this paper, an software verification and validation (V&V) activities for DRPS, which are independent of the DRPS development processes, are described according to the software development life cycle. The main activities of DRPS V&V processes are the software planning documentations, the verification of software requirements specification (SRS) and software design specification (SDS), the verification of codes, the tests of the integrated software and system. Moreover, the software safety analysis and the software configuration management are involved in the DRPS V&V processes. All of the V&V activities are described, in detail, in this paper.

• Journal of the Korean Institute of Gas
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• v.20 no.6
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• pp.80-88
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• 2016

A fire station and scuba have operated filling facilities for respiratory high-pressure cylinder without getting authority or reporting according to High-Pressure Gas Safety Control Act. They need facility improvement and special management to make provision for the time of accident during filling process. The Government have strived to correct illegal operations and suggested an alternative, establishing and operating the safety cabinet. It insures a safety being distance from danger caused by overpressure and a safety provoked by the protective wall equals or superiors. The safety cabinet is required to have an internal structure that smoothly distribute overpressure at the time of rupture. Plus, it needs to minimize fragments. It is also equipped with the performance of protective wall that makes overpressure to outside vent on the place where there is no person (top or bottom). This study calculated the consequence of physical explosion damage and built a prototype of safety cabinet. In addition, through the gas burst test, it derives for the ways to mitigate the physical explosion damage.

• Fire Science and Engineering
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• v.23 no.4
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• pp.67-72
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• 2009

For the fire-fighting industry to advance, it is necessary to conduct research on which parts of the fire-fighting law should be changed from the system level, and to study the opinions of the fire-fighters whoa re working in the fire-fighting industry today, and to identify what needs to be changed. Moreover, it is necessary to become aware on the preventive measures to take to avoid fire so that the citizens can lead stable life. Design business among the fire-fighting facility business, it is the fire-fighting facility business that serves as the most basic when constructing building structure. This is an important legal matter that follows the fire-fighting business, fire-fighting audit business and even the maintenance and management business. This research sought to help the fire-fighting industry to contribute to the life of the general public and to increase welfare by identifying the problems pertaining to the fire-fighting facility design business among the fire-fighting industry so that the industry can become the fire-fighting industry that the citizens are interested in. Moreover, direction for advancement is proposed. As for the improvement measures for the fire-fighting policy pertaining to the fire-fighting facility design business, it is divided into the machinery and electricity fields in terms of the legal system pertaining to the general fire-fighting facility design business. Likewise, specialty in design is deficient. Thus, it should be integrated in a systematic level to contribute to the safety of the general public.

• Journal of the Korea Academia-Industrial cooperation Society
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• v.21 no.3
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• pp.190-198
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• 2020

For domestic urban railways, which have a 19.7% aging rate, a performance evaluation is necessary to establish capital improvement investment plans. The performance evaluation, which was recently enacted in the relevant law, points out the excessive time and effort for acquiring data and evaluation. This study developed a performance evaluation simulation prototype using a virtual reality (VR) method to use as training contents for railway performance evaluations. The practical use of the VR technique to reduce the working time under poor environment conditions was confirmed through a literature review. A survey and consultation were conducted for urban railway experts to determine the weight of the performance evaluation items and the facility breakdown structure. This information was utilized to develop performance evaluation sheets for simulation. Based on the evaluation sheet, a training content prototype that evaluates the performance of platform safety doors was developed using VR techniques with HTC VIVE equipment. VR simulation tests were conducted for six players, and the prototype was sufficiently advantageous for a visual confirmation of the facility information. The result is expected to be useful for engineers to understand the performance evaluation process efficiently before an actual performance evaluation of urban railway facilities.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.15 no.3
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• pp.257-264
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• 2017

For the safe disposal of intermediate level radioactive waste according to the Nuclear Safety and Security Commission's notice and KORAD's management plan for low and intermediate level radioactive waste, the disposal concentration limit was derived based on the IAEA methodology. The evaluation of the derived disposal concentration limit revealed that it is not suitable as a practical limit for intermediate level radioactive waste. This is because the disposal concentration limit according to the IAEA methodology is derived using a single value of radioactive waste density and the disposal facility's volume. The IAEA methodology is suitable for setting the concentration limit for vault type disposal, which consists of a single type of waste, whereas an underground silo type disposal facility is composed of several types of radioactive waste, and thus the IAEA methodology has limitations in determining the disposal concentration limit. It is necessary to develop and apply an improved method to derive the disposal concentration limit for intermediate level radioactive waste by considering the radioactivity of various types of radioactive waste, the corresponding scenario evaluation results, and the regulatory limit.