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| 1 |
Investigation of Steam Generator Tube Stress Corrosion Cracking Induced by Lead
Kim, Dong-Jin;Hwang, Seong Sik;Kim, Joung Soo;Kim, Hong Pyo;
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Korean Society of Pressure Vessels and Piping
, v.5, no.2, pp.1-6,
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| 2 |
A Study on the Crack Depth Sizing Using ECT Technique for Martensitic Stainless Steel
Kim, Wang-Bae;Cheon, Keun-Young;
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Korean Society of Pressure Vessels and Piping
, v.5, no.2, pp.7-12,
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| 3 |
Development of CANDU Reactor Aging Monitor
Kim, Hong Key;Choi, Young Hwan;Ko, Han Ok;
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Korean Society of Pressure Vessels and Piping
, v.5, no.2, pp.13-19,
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| 4 |
Damage Type and Remaining Strength of Damaged Pipelines due to the Third Party Interference
Kim, Young Pyo;Baek, Jong Hyun;Kim, Cheol Man;Kim, Woo Sik;
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Korean Society of Pressure Vessels and Piping
, v.5, no.2, pp.20-26,
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| 5 |
A Numerical Ductile Failure Simulation Technique Based on Phenomenological Damage Concept
Kim, Nak-Kyun;Oh, Chang-sik;Min, Sung-hwan;Kim, Yun-Jae;
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Korean Society of Pressure Vessels and Piping
, v.5, no.2, pp.27-34,
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| 6 |
Development of the Event Type Analysis System (ETAS) for the Accident Evaluation in Nuclear Power Plants
Choi, Young Hwan;Kim, Young Mi;
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Korean Society of Pressure Vessels and Piping
, v.5, no.2, pp.35-39,
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| 7 |
Development of Event Corrective Action Supporting System (ECAS) in Nuclear Power Plant
Choi, Young Hwan;Kim, Yopng Mi;Ko, Han Ok;
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Korean Society of Pressure Vessels and Piping
, v.5, no.2, pp.40-44,
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