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1 |
Development the Preventive Maintenance Template of the Nuclear Steam Turbine based on EPRI PMBD
Lee, Byoung Hak;Lee, Hyuk Soon;
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Korean Society of Pressure Vessels and Piping
, v.6, no.1, pp.1-8,
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2 |
The Study of Visual Tool for Automated Ultrasonic Examination of the Piping Welds in NPP
Yoo, Hyun Joo;Choi, Sung Nam;Kim, Hyung Nam;Lee, Hee Jong;
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Korean Society of Pressure Vessels and Piping
, v.6, no.1, pp.9-15,
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3 |
Development of Phased Array Ultrasonic Testing Technique for Nuclear Power Plant Cast Piping Weld
Yoon, Byungsik;Yang, Seunghan;Kim, Yongsik;
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Korean Society of Pressure Vessels and Piping
, v.6, no.1, pp.16-22,
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4 |
Generic Procedure Development for the Ultrasonic Examination of Dissimilar Metal Welds in Nuclear Power Plants
Yang, Seung Han;Kim, Yong Sik;Yoon, Byung Sik;Guon, Kee Il;
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Korean Society of Pressure Vessels and Piping
, v.6, no.1, pp.23-28,
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5 |
UT Inspection Technique of Cast Stainless Steel Piping Welds Using Low Frequency TRL UT Probe
Shin, Keon-Cheol;Chang, Hee-Jun;Jeong, Young-Cheol;Noh, Ik-Jun;Lee, Dong-Jin;
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Korean Society of Pressure Vessels and Piping
, v.6, no.1, pp.29-36,
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6 |
Field Application of Ultrasonic Inspection System for Stay Welds at Steam Generator of KSNP
Lim, Sa Hoe;Park, Chi Seung;Park, Chul Hoon;Joo, Keum Chong;Noh, Hee Chung;Yoon, Kwang Sik;
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Korean Society of Pressure Vessels and Piping
, v.6, no.1, pp.37-42,
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7 |
Evaluation of Piping Failure Probability of Reactor Coolant System in Kori Unit 1 Considering Stress Corrosion Cracking
Park, Jeong Soon;Choi, Young Hwan;Park, Jae Hak;
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Korean Society of Pressure Vessels and Piping
, v.6, no.1, pp.43-49,
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8 |
Fatigue Life Analysis of SA508 Gr. 1A Low-Alloy Steel under the Operating Conditions of Nuclear Power Plant
Lee, Yong Sung;Kim, Tae Soon;Lee, Jae Gon;
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Korean Society of Pressure Vessels and Piping
, v.6, no.1, pp.50-56,
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9 |
High-temperature Structural Analysis on the Small Scale PHE Prototype
Song, Kee-nam;Lee, H-Y;Hong, S-D;Park, H-Y;
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Korean Society of Pressure Vessels and Piping
, v.6, no.1, pp.57-64,
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10 |
Heat Transfer Study to Replace a Tube Bundle of Moisture Separator Reheater at Nuclear Power Plant
Choi, You-Sung;Choi, Kwang-Hee;Lee, Sang-Guk;
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Korean Society of Pressure Vessels and Piping
, v.6, no.1, pp.65-71,
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11 |
Development of Remote Visual Inspection Technology for Calandria & Internal of CANDU NPP
Lee, Sang-Hoon;Jin, Seuk-Hong;Moon, Gyoon-Young;
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Korean Society of Pressure Vessels and Piping
, v.6, no.1, pp.72-77,
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12 |
Analysis of Defect in CANDU Feeder Pipe using Phased Array Ultrasonic Inspection System
Lee, Sang-Hoon;Jin, Seuk-Hong;Kim, In-chul;
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Korean Society of Pressure Vessels and Piping
, v.6, no.1, pp.78-82,
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13 |
Root Cause Analysis of Axial ODSCC of Steam Generators Tubes of OPR1000
Kim, Hong-deok;Park, Su-ki;Yim, Chang Jae;Chung, Han Sub;
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Korean Society of Pressure Vessels and Piping
, v.6, no.1, pp.83-88,
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