• Journal of Radiation Industry
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• v.18 no.3
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• pp.223-226
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• 2024

It is essential to precisely evaluate the expected dose (collective dose) before performing high-exposure tasks in nuclear power plants because those have a high potential to cause significant radiation exposure to workers. A dose evaluation method is to design the scenarios of high-exposure tasks using computational codes, which allows for the calculation of the expected collective dose. Although these computational scenarios are useful for estimating the expected radiation dose and establishing radiation protection plans, the calculated doses may not perfectly match the actual doses that workers receive during tasks due to differences between the scenario and the actual circumstances in the radiation fields. Therefore, this study presents a methodology for calculating correction factors to improve the accuracy of dose predictions from computational scenarios. This approach aims to make the predicted collective dose before the task closer to the actual dose received by workers, thereby enhancing radiation safety for personnel performing high-exposure tasks. Additionally, these correction factors will help accurately predict doses under various working conditions in the future, contributing to minimizing radiation exposure risks for nuclear power plant workers.

• Nuclear Engineering and Technology
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• v.43 no.1
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• pp.45-62
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• 2011

The Korean nuclear industry is developing a thermal-hydraulic analysis code for safety analysis of pressurized water reactors (PWRs). The new code is called the Safety and Performance Analysis Code for Nuclear Power Plants (SPACE). The SPACE code adopts advanced physical modeling of two-phase flows, mainly two-fluid three-field models which comprise gas, continuous liquid, and droplet fields and has the capability to simulate 3D effects by the use of structured and/or nonstructured meshes. The programming language for the SPACE code is C++ for object-oriented code architecture. The SPACE code will replace outdated vendor supplied codes and will be used for the safety analysis of operating PWRs and the design of advanced reactors. This paper describes the overall features of the SPACE code and shows the code assessment results for several conceptual and separate effect test problems.

• Transactions of the Korean Society of Mechanical Engineers A
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• v.28 no.6
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• pp.663-669
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• 2004

A nuclear power plant is composed of a number of primary components. Maintaining the integrity of these components is one of the most critical issues in nuclear industry. In order to maintain the integrity of these primary components, a complicated procedure is required including regular in-service inspection, failure assessment, fracture mechanics analysis, etc. Also, experts in different fields have to co-operate to resolve the integrity issues on the basis of inspection results. This integrity evaluation process usually takes long, and thus, is detrimental for the plant productivity. Therefore, an effective safety evaluation system is essential to manage the integrity issues on a nuclear power plant. In this paper, a web-based fatigue life evaluation system for primary components in nuclear power plant is proposed. This system provides engineering knowledge-based information and concurrent and collaborative working environment through internet, and thus, is expected to raise the efficiency of integrity evaluation procedures on primary components of a nuclear power plant.

• Proceedings of the KSME Conference
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• 2003.04a
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• pp.279-284
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• 2003

A nuclear power plant is composed of a number of primary components. Maintaining the integrity of these components is one of the most critical issues in nuclear industry. In order to maintain the integrity of these primary components, a complicated procedure is required including regular in-service inspection, failure assessment, fracture mechanics analysis, etc. Also, experts in different fields have to co-operate to resolve the integrity issues on the basis of inspection results. This integrity evaluation process usually takes long, and thus, is detrimental for the plant productivity. Therefore, an effective safety evaluation system is essential to manage the integrity issues on a nuclear power plant. In this paper, a web-based fatigue life evaluation system for primary components in nuclear power plant is proposed. This system provides engineering knowledge-based information and concurrent and collaborative working environment through internet, and thus, is expected to raise the efficiency of integrity evaluation procedures on primary components of a nuclear power plant.

• Korean Journal of Construction Engineering and Management
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• v.16 no.3
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• pp.101-112
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• 2015

In the 1950s, the concept of configuration management (CM) was started by the US Department of Defense (DOD). Later, it has begun to be applied in aerospace, software, engineering, construction, and nuclear power industry. However, configuration management (CM) in the Korean nuclear industry was firstly utilized in 2006 only for selected parts of facilities, while the US nuclear industry has applied CM for the facilities' entire systems since 1990s. Furthermore, configuration management (CM) is in its conceptual stage in the Korean nuclear industry because of ambiguous CM concepts, lacks of CM professional manpower, non-computerization, and inadequacy of CM procedures and processes. In order to address this issues, seven industries (including defense, aerospace, software, engineering, architecture, civil engineering, nuclear power) that utilize the concept of configuration management (CM) were compared and analyzed based on the CM purpose, technique, and life-cycle perspectives. By an extensive literature review and expert interviews, this paper developed a framework of configuration management (CM) for the nuclear industry. And also, a list of functions based on life-cycle stages and CM techniques are developed for clarifying CM framework in order to promote practical applications.

• Journal of Radiation Industry
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• v.10 no.1
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• pp.7-12
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• 2016

Ikaros, a transcription factor containing zinc-finger motif, has known as a critical regulator of hematopoiesis in immune system. Ikaros protein modulates the transcription of target genes via binding to the regulatory elements of the genes promoters. However the regulatory function of Ikaros in other organelle except nuclear remains to be determined. This study explored radiation-induced modulatory function of Ikaros in cytoplasm. The results showed that Ikaros protein lost its DNA binding ability after LDIR (low-dose ionizing radiation) exposure. Cell fractionation and Western blot analysis showed that Ikaros protein was translocated into cytoplasm from nuclear by LDIR. This was confirmed by immunofluorescence assay. We identified Autotaxin as a novel protein which potentially interacts with Ikaros through in vitro protein-binding screening. Co-immunoprecipitation assay revealed that Ikaros and Autotaxin are able to bind each other. Autotaxin is a crucial enzyme generating lysophosphatidic acid (LPA), a phospholipid mediator, which has potential regulatory effects on immune cell growth and motility. Our results indicate that LDIR potentially regulates immune system via protein-protein interaction of Ikaros and Autotaxin.

• Journal of Radiation Industry
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• v.17 no.4
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• pp.427-436
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• 2023

As a result of evaluating the level of tritium emitted from the nuclear power plant in the environment and the human body, it was confirmed that tritium was detected in the environmental media and human urine samples to be investigated. It was found that the tritium was clearly detected. After the operation of the Tritium Removal Facility (TRF), which was operated for the purpose of removing tritium from the Wolsong nuclear power plant, the tritium emission showed a decreasing trend, and the tritium level in the environmental media also showed a tendency to decrease accordingly. However, for precise evaluation, it was necessary to select and investigate points by distance, season, and wind direction from the nuclear power plant, but it also showed characteristics that did not reflect this. As the cycle, etc., implemented the previous environmental monitoring program as it is, there was also a limitations in not being able to reflect the changing environment. Therefore, it is necessary to review and supplement the environmental monitoring investigation plan and results so far, and by applying the supplemented investigation plan to secure valid and reliable investigation results, it is judged that it will be an appropriate measure for environmental conservation and human protection in the vicinity of the nuclear power plant.

• Proceedings of the Korean Nuclear Society Conference
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• 1997.05a
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• pp.251-256
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• 1997

The safety and reliablity of nuclear power plant operations relies heavily on the plant operators ability to respond to various emergency situations. It has become standard industry practice to utilize simulators to improve the safety and reliability of nuclear power plants operations. The simulators built for Younggwang#3("YGN#3"), which is based on the Korean Standard Nuclear Power Plant ("KSNPP")design, has been developed precisely for this purpose. The YGN#3 simulator is the first simulator in Korea to be developed locally and is now operational on site. A particular attention was placed on the development of CPC/COLLS safety system which is unique to the YGN#3. The effort to develop CPC/COLLS simulation model has been successful and plans exist for applying this model to simulator projects in the future.jects in the future.

• Korean Journal of Computational Design and Engineering
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• v.6 no.2
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• pp.140-146
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• 2001

A nuclear Power Plant is composed of a number of mechanical components. Maintaining the integrity of these components is one of the most critical issues in nuclear industry. In order to evaluate the integrity of these mechanical components, a lot of data are required including inspection data, geometrical data, material properties, etc. Therefore, an effective database system is essential to manage the integrity of nuclear power plant. For this purpose, an internet based virtual reality environment and web database system was proposed. The developed virtual reality environment provides realistic geometrical configurations of mechanical components using VRML (Virtual Reality Modeling Language). The virtual reality environment was linked with the web database, which can manage the required data for the integrity evaluation. The proposed system is able to share the information regarding the integrity evaluation through internet, and thus, will be suitable for an integrated system for the maintenance of mechanical components.

• JOURNAL OF ELECTRICAL WORLD
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• no.7 s.103
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• pp.2-5
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• 1985