• Proceedings of the Korean Institute of Industrial Safety Conference
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• 2005.10a
• /
• pp.216-221
• /
• 2005

• Proceedings of the Korean Nuclear Society Conference
• /
• 1998.10a
• /
• pp.372-372
• /
• 1998

• Proceedings of the Korean Nuclear Society Conference
• /
• 2004.05a
• /
• pp.150.2-150.2
• /
• 2004

• Proceedings of the SAREK Conference
• /
• 2007.06a
• /
• pp.11-11
• /
• 2007

• Proceedings of the Korean Nuclear Society Conference
• /
• 1996.05d
• /
• pp.455-460
• /
• 1996

원자력발전소의 전열관 보수용접 기술 개발을 위해 Inconel 600 재질의 plate 판에 레이저 용접실험을 수행하였다. 레이저 발진기로 부터 발진된 레이저 빔은 광섬유를 통하여 전송되고, 집광렌즈군를 이용하여 용접이 이루어지도록 하였다. pulse 레이저 용접 변수인 펄스폭, 반복율, 첨두출력 및 용접속도를 변화시키면서 용접결과를 측정하였다. 이에 따른 적절한 용접범위를 제시하였다.

• Proceedings of the Korean Institute of Industrial Safety Conference
• /
• 2004.04a
• /
• pp.10-15
• /
• 2004

• Proceedings of the Korean Magnestics Society Conference
• /
• 2005.12a
• /
• pp.40-42
• /
• 2005

• Proceedings of the Korean Radioactive Waste Society Conference
• /
• 2011.10a
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• pp.311-312
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• 2011

• Transactions of the Korean Society of Pressure Vessels and Piping
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• v.6 no.2
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• pp.16-19
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• 2010

In this study, the axial ODSCC occurrence of domestic OPR 1000 steam generator tube was caused by the tube weakness and the sludge accumulation in the secondary side of steam generator. Inconel 600 HTMA used as tube material is related to most of tube leakage accidents in the world and also these ODSCCs were detected mainly at the 5th TSP(Tube Support Plate) to the 8th TSP of hot leg side. These elevations(5th TSP to 8th TSP) pave the way for the sludge accumulation. As a result of EC(Eddy Current) Bobbin and RPC data analysis, ODSCCs were occurred at contact points of tube and tube support plate. The more accumulated sludge, the higher occurrence frequency of ODSCC.

• Transactions of the Korean Society for Noise and Vibration Engineering
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• v.26 no.2
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• pp.203-209
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• 2016

According to the wear detection history for the steam generator tubes in the nuclear power plant, the outer tubes inside the steam generator have more problems on the flow-induced vibration than inner tubes. Many researchers and engineers have used a specified added mass coefficient for a given tube array during the design stage of the steam generator even though the coefficient is not constant for entire tube in cylindrical shell. The aim of this study is to find out the distribution of added mass coefficients for each tube along the radial location. When numbers of tubes inside a cylindrical shell are increased, values of added mass coefficients are also increased. Added mass coefficients at outer tubes are less than those of inner tubes and they are decreased with increasing the gap between the outermost tube and the cylindrical shell. It also turns out when the gap between the outermost tube and the cylindrical shell approaches infinite value, the added mass coefficient converges to an asymptotic value of given tube array in a free fluid field.