• Journal of Radiation Protection and Research
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• 제28권4호
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• pp.349-351
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• 2003

To ensure the safety of the currently operating nuclear power plant, the Periodic Safety Review program has been conducted. In PSR program, the cumulative behavior of the radionuclide that might be released from the power plant is addressed. The Cs-137 in soil around Kori nuclear power plant was investigated. The soil sample was analyzed and compared with the reference area. The model calculation explained the depth profile of Cs-137.

• 한국압력기기공학회 논문집
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• 제18권2호
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• pp.50-53
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• 2022

To investigate the validity of the finite element analysis program to assess structural integrity of a spent nuclear fuel transport cask subjected to extreme impact loads, structural integrity of the cask for the case of an aircraft engine collision is evaluated using three FE analysis programs: Autodyn, Speed and ABAQUS explicit version. As a result of all analyses, it is confirmed that no penetration occurred in the cask wall. Even though the different programs are used, it is identified that there are insignificant differences in the FE analysis variables such as von Mises effective stress and equivalent plastic strain among the programs.

• Nuclear Engineering and Technology
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• 제55권1호
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• pp.364-372
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• 2023

The space reactor is the primary energy supply for future space vehicles and space stations. The radiator is one of the essential parts of a space reactor. Therefore, the research on radiators can improve the heat dissipation power, reduce the quality of radiators, and make the space reactor smaller. Based on MOOSE multi-physics numerical calculation platform, a simulation program for the combination of heat pipe and fin at the end of heat pipe radiator is developed. It is verified that the calculation result of this program is accurate and the calculation speed is fast. Analyze the heat transfer characteristics of the combination with heat pipe and fin, and obtain its internal temperature field. Based on the calculation results, the influence of structural parameters on the heat dissipation power is analyzed. The results show that when the fin width is 0.25 m, fin thickness is 0.002 m, condensing section length is 0.5425 m and heat pipe radius is 0.014 m, the power-mass ratio is the highest. When the temperature is 700K-900K, the heat dissipation power increases 41.12% for every 100K increase in the operating temperature. Smaller fin width and thinner fin thickness can improve the power-mass ratio and reduce the radiator quality.

• 방사성폐기물학회지
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• 제18권spc호
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• pp.51-62
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• 2020

In this paper, an approach developed by the Finnish nuclear waste management organization, Posiva, for the construction license of a geological repository was reviewed. Furthermore, a computer program based on the approach was developed. By using the computer program, the lifetime of a copper disposal canister, which was a key engineered barrier of the geological repository, was predicted under the KAERI Underground Research Tunnel (KURT) geologic conditions. The computer program was developed considering the mass transport of corroding agents, such as oxygen and sulfide, through the buffer and backfill. Shortly after the closure of the repository, the corrosion depths of a copper canister due to oxygen in the pores of the buffer and backfill were calculated. Additionally, the long-term corrosion of a copper canister due to sulfide was analyzed in two cases: intact buffer and eroded buffer. Under various conditions of the engineered barrier, the corrosion lifetimes of the copper canister due to sulfide significantly exceeded one million years. Finally, this study shows that it is necessary to carefully characterize the transmissivity of rock and sulfide concentration during site characterization to accurately predict the canister lifetime.

• 대한안전경영과학회:학술대회논문집
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• 대한안전경영과학회 2004년도 추계학술대회
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• pp.277-287
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• 2004

This study presents a method of quality category classification by safety, maturity, complexity, and what types and extent of controls and verifications are applied to specific products and services during the various stages of a nuclear facility life cycle. All products, services and processes have various controls and verifications built in to ensure they perform their functions satisfactorily. The highest grade should require the most stringent application of the quality assurance requirements ; while, the lowest grade should require the least stringent. When products or services are modified, the assigned grade of quality assurance requirements could become more stringent or less stringent depending on the significance in nuclear safety. Applying QA program always costs money, and they should be applied and focused to the extent where necessary and not applied or applied to a lesser degree for less important activities. An efficient QA program should be developed to satisfy the necessary requirements and to ensure the required confidence in quality, but without unnecessary stipulations. Not all the requirements of QA standard must be applied identically to all products and services which are to be provided.

• 한국콘크리트학회:학술대회논문집
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• 한국콘크리트학회 2006년도 추계 학술발표회 논문집
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• pp.237-240
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• 2006

Almost 30 years have been passed since the first nuclear power plant was operated in Korea. Many studies have been actively conducted from the early 1990's in order to develop the deterioration management system for concrete structures in NPPs(Nuclear Power Plants) accordingly. Base on these studies, a systematic deterioration management program has developed and operated since 1997. According to this program, systematic inspections to provide database and evaluation were periodically performed (every overhaul at intervals of $12{\sim}18$ month and every five years). Accumulated deterioration database was usefully utilized for the NPP PSR (Periodic Safety Review). In this paper, the long-term durability and integrity of Kori 1,2 NPP concrete structures which are the oldest ones in Korea were evaluated based on the precise inspection database and regulatory inspection results including compressive strength, depth of carbonation, amount of chlorination and spontaneous potential of reinforcing bar, etc. It was noted that Kori 1,2 NPP structures have not any serious durability problems.

• Corrosion Science and Technology
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• 제17권6호
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• pp.317-323
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• 2018

Assumptions have always been that wall thinning on the secondary side piping in nuclear power plants is mostly caused by Flow-Accelerated Corrosion (FAC). Recent studies have showed that wall thinning on the secondary side piping is caused by Liquid Droplet Impingement Erosion (LDIE), Solid Particle Erosion (SPE), cavitation, and flashing. To manage those aging mechanisms, several software such as CHECWORKS, COMSY, and BRT-CICERO have been used in nuclear power plants. Korean nuclear power plants have been using the CHECWORKS program since 1996 to date. However, many site engineers have experienced a lot of inconveniences and problems in using the CHECWORKS program. In order to work through the inconveniences and to remedy problems, KEPCO-E&C has developed a "3D-based pipe wall thinning management program (ToSPACE)" based on the experience of over 30 years in relation to the pipe wall thinning management. This study compares the results of FAC and LDIE analysis using both the CHECWORKS and ToSPACE programs with respect to validation of the wall thinning analysis results.

• 핵의학기술
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• 제14권2호
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• pp.166-171
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• 2010

SPECT/CT는 SPECT의 기능학적 영상과 CT의 해부학적인 영상의 융합(Fusion)을 통하여 기존의 SPECT에서 병소의 위치 및 범위를 감별하는데 어려웠던 문제들을 해결하여 진단적 정보에 도움을 줄수 있다. Infinia Hawkeye 4 (GE Healthcare)의 SPECT/CT 감마카메라 영상과 진단용 CT영상을 융합(Fusion)하여 3D (three Dimension)로 Rendering 할 수 있는 Volumetrix Suite의 유용성을 소개하고자 한다. 본원에 SPECT/CT 검사를 하기 위해 내원한 환자 중, 동일한 검사부위의 진단용 CT영상이 있는 환자(Bone, Venography, Parathyroid, WBC)를 대상으로 Volumetrix Suite (Volumetrix IR, Volumetrix 3D)를 적용하였다. Infinia Hawkeye 4의 SPECT영상과 CT영상을 획득한 후 두 영상을 2D (two Dimension)로 융합(Fusion)하였다. Infinia Hawkeye4 SPECT/CT에서의 CT는 해부학적 정보에 한계가 있어, 3D (three Dimension) Rendering을 하기 위해서는 정보량이 많은 진단용 CT영상을 PACS상에서 DICOM (Digital Imaging and Communications in Medicine) File로 전송하여 Infinia Hawkeye4의 Xeleris Workstation에서 IR (Image Registration)한 후 Intergrating 3D (three Dimension)로 융합(Fusion)하여 2D(two Dimension)영상을 3D (three Dimension)영상으로 Rendering하였다. Volumetrix Suite program을 이용함으로써 Infinia Hawkeye 4의 SPECT/CT 영상과 별도로 촬영한 고해상도 진단용 CT영상을 3D Rendering하여 병소의 위치 및 범위를 감별하는데 좀 더 명확한 해부학적 정보를 얻을 수 있었다. 따라서, 해부학적인 정보가 부족한 핵의학영상을 보완함으로서 더 많은 정보를 제공해 핵의학영상 검사의 진단능력을 향상시킬 수 있을 것이라고 기대된다.

• Journal of Radiation Protection and Research
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• 제45권4호
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• pp.147-153
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• 2020

Background: Malawi's 2018 National Energy Policy includes nuclear power as an energy option with an operational 100 MW targeted for 2035. Materials and Methods: This paper challenges the scope of the policy on nuclear power by reviewing its implementation strategy and comparing it to: the strategy established for coal in the same policy; some experiences from other countries; and documents by the International Atomic Energy Agency (IAEA) relating to establishing a national position on nuclear power and infrastructural requirements for a nuclear power program. Results and Discussion: It is found that the pro-nuclear position is uninformed, and targets are unrealistic owing to a lack of understanding of nature of nuclear power including the requirements for safety, security and safeguards, and nuclear infrastructure. It is apparent that neither consultation nor a proper analysis were comprehensively conducted for nuclear. Though the national energy policy suggests a national position for nuclear energy, the content does not demonstrate that the position was arrived at knowledgeably. Conclusion: Thus, nuclear power may presently be viewed as a potential energy option that is yet to be seriously considered. It is important to build an appropriate level of literacy on nuclear science and technology for policy makers, key stakeholders, and the public to be better positioned for strategizing on nuclear power.

• 대한인간공학회지
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• 제32권1호
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• pp.107-115
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• 2013

Objective: The aim of this study is to identify the training requirements of new nuclear power plant by a comprehensive literature review. Background: The design of instrumental and control systems for New NPP is applied fully digitalized systems. For example, soft-control, large display panels(LDP), and an advanced alarm system were applied to the APR-1400 or SMART. Method: The NUREG-0711 and international guideline of training program was analyzed from the following four phases of SAT(Systemic Approach to Training): Analysis, Design, Development, Implementation and Evaluation. Results: To identify the requirement of training program, 'Feedback' phase was considered and each phase of SAT was classified. Conclusion: A more systematic requirement of training program is needed which considers the computerized system was applied to the new NPP. Application: The results of the publishing can be useful for standardization of the systematic training program for the operators of NPP.