• Proceedings of the Korean Society of Precision Engineering Conference
• /
• 2008.06a
• /
• pp.179-180
• /
• 2008

• Proceedings of KOSOMES biannual meeting
• /
• 2017.04a
• /
• pp.111-111
• /
• 2017

• Proceedings of the Korean Radioactive Waste Society Conference
• /
• 2017.05a
• /
• pp.155-156
• /
• 2017

In this study, the structural integrity of the spent nuclear fuel assemblies was evaluated by carrying out a 0.3 m drop impact analysis, one of the normal transportation conditions of the nuclear fuel assemblies. For this purpose, the spent nuclear fuel assembly was modeled in detail as beam elements, and a coupled model for impact analysis was developed by inserting the modeled nuclear fuel assemblies into a cask.

• Proceedings of the Korean Society of Precision Engineering Conference
• /
• 2013.05a
• /
• pp.1181-1182
• /
• 2013

• Journal of Korean Academy of Nursing
• /
• v.31 no.6
• /
• pp.1109-1118
• /
• 2001

The purpose of this study was to analyze the appraising frame and the accreditation system of universities in both Korea and the United Sates, as well as developing a standard plan to appraise 4 year nursing education institutions in Korea. Research design of this study was descriptive comparative research. The results of the research can be divided into six fields, educational purposes, educational courses, students, faculty, facility .equipments and administration.finance in Korea. Then the results were further categorized into seven fields : mission and governance, faculty, students, curriculum and instruction, resources, educational effectiveness and integrity. Thus Korean appraising frames were suggested to have eight fields of standard. The fields are philosophy and purposes of educational institution, educational courses and instruction, students, faculty, facility .equipments, adminstration.finance, educational effectiveness and integrity.

• Transactions of the Korean Society of Mechanical Engineers
• /
• v.19 no.3
• /
• pp.731-740
• /
• 1995

The objective of this paper is to develop defect assessment technology for integrity evaluation of CANDU pressure tubes. In fracture mechanics analysis, three-dimensional and two-dimensional (line-spring model) finite element analyses were performed to obtain the stress intensity factor for axial and circumferential surface cracks. In leak before break (LBB) analysis, heat transfer analyses for through-wall cracks were performed by considering the cooling effect and the LBB application time was computed. It was shown that the analytical results obtained in this study provide less-conservative but accurate solution for defect assessment of CANDU pressure tubes.

• Journal of the Korean Society for Railway
• /
• v.9 no.5 s.36
• /
• pp.594-600
• /
• 2006

In this study, transient and quasi-static analysis were done for the evaluation of structural integrity of the platform screen door due to train wind pressure. Fluent 6.0 was used to calculate the train wind pressure, and Ansys 10.0 was used to evaluate the structural stability of platform screen door due to train wind pressure. Transient analysis was used to check the design requirements of platform screen door, and quasi-static analysis was introduced to save the calculating time and check quickly structural performances when compared to those of transient analysis. The results show that structural stability of the platform screen door under train wind pressure is proven and quasi-static analysis can quickly check the structural integrity of platform screen door.

• Transactions of the Korean Society of Pressure Vessels and Piping
• /
• v.13 no.2
• /
• pp.44-50
• /
• 2017

The shaft seal of the reactor coolant pump is installed on the upper side of the rotating shaft of the pump to seal the reactor coolant from flowing out between the rotating shaft and the non-rotating parts. In this study, the loading conditions for the normal operation and faulted conditions are identified and structural integrity evaluation is performed using the finite element stress analysis for the sealing apparatus of the APR 1400 reactor coolant pump. It is confirmed that the stress analysis results satisfy the design criteria at all loading conditions.

• Journal of the Korean Institute of Illuminating and Electrical Installation Engineers
• /
• v.19 no.2
• /
• pp.94-99
• /
• 2005

This paper presents the integrity evaluation method of the windings in cast resin transformers using vertical thermal distribution analysis. The method is the result from comparing the temperature distribution in a sound condition specimen with that in the failure condition specimen layer-shorted by accelerated testing. The temperature distribution was acquisited by a infrared thermography system, and the Arrhenius equation was adopted to the accelerated testing. The proposed method may be available to detect the failures in cast resin transformers.

• Nuclear Engineering and Technology
• /
• v.34 no.2
• /
• pp.105-116
• /
• 2002

In special industrial fields such 3s nuclear power plants and chemical plants, it is often necessary to repair system components without plant shutdown or drainage of system having many piping structures which may have hazardous or expensive fluid. A temporary ice plugging method for blocking internal flow is considered as a useful method in that case. According to the pipe freezing guideline of the nuclear power plant, the length of a freezing jacket must be longer than twice of the pipe diameter. However, for applying the ice plugging to short pipes which do not have enough freezing length because of geometrical configuration, it is inevitable to use shorter jacket less than twice of the pipe diameter. In this study, the integrity evaluation for short pipes in the nuclear power plant Is conducted by an experiment and the finite element analysis. From the results, the ice plugging process in short pipes can be safely carried out without any plastic deformation and fracture.