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| 1 |
A Study on the Functional Importance Determination Methodology for Components in Nuclear Power Plants
Song, Tae-Young;
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Korean Society of Pressure Vessels and Piping
, v.9, no.1, pp.1-7,
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| 2 |
Feasibility Study for Low Pressure Turbine Inspection of Nuclear Power Plant Using Shear Wave Phased Array Ultrasonic Transducer
Yoon, Byung Sik;Kim, Yong Sik;Kim, Jin Hoi;
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Korean Society of Pressure Vessels and Piping
, v.9, no.1, pp.8-14,
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| 3 |
A Safety Improvement for the Design Change of Westinghouse 2 Loop Auxiliary Feedwater System
Na, Jang Hwan;Bae, Yeon Kyoung;Lee, Eun Chan;
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Korean Society of Pressure Vessels and Piping
, v.9, no.1, pp.15-19,
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| 4 |
Development of Safety Review Guide for Periodic Safety Review of Reactor Vessel Internals
Lee, Ki Hyoung;Park, Jeong Soon;Ko, Han Ok;Jhung, Myung Jo;
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Korean Society of Pressure Vessels and Piping
, v.9, no.1, pp.20-24,
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| 5 |
Evaluation on the Effect of Ultrasonic Testing due to Internal Medium of Pipe in Nuclear Power Plant
Yoon, Byung Sik;Kim, Yong Sik;Yang, Seung Han;
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Korean Society of Pressure Vessels and Piping
, v.9, no.1, pp.25-30,
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| 6 |
KHNP-JIT Development for the Effective Use of Nuclear Power Plant Operating Experiences
Hur, Nam Young;Lee, Sang Hoon;Kim, Je Hun;
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Korean Society of Pressure Vessels and Piping
, v.9, no.1, pp.31-34,
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| 7 |
An Analysis of Operating Experience Reports Published in the Domestic Nuclear Power Plants for Resent 5 Years
Lee, Sang-Hoon;Kim, Je-Hun;Hur, Nam-Young;
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Korean Society of Pressure Vessels and Piping
, v.9, no.1, pp.35-39,
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| 8 |
A Development of Eddy Current Testing System for Steam Generators Inspection in Nuclear Power Plants
Moon, Gyoon-Young;Cho, Chan-Hee;Yoo, Hyun-Joo;Lee, Tae-Hun;Cho, Yong-Bae;
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Korean Society of Pressure Vessels and Piping
, v.9, no.1, pp.40-47,
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| 9 |
Development of Web-based Design Compatibility Assessment Program for High Temperature Reactor
Cho, Doo Ho;Surh, Han Bum;Choi, Jae Boong;Huh, Nam Su;Choi, Young Hwan;
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Korean Society of Pressure Vessels and Piping
, v.9, no.1, pp.48-55,
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| 10 |
Root Cause Analysis and Structural Integrity Evaluation for a Crack in a Reactor Vessel Upper Head Penetration Nozzle
Lee, Kyoung-Soo;Lee, Sung-Ho;Lee, Jeong-Seog;Lee, Jae-Gon;Lee, Seung-Gun;
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Korean Society of Pressure Vessels and Piping
, v.9, no.1, pp.56-61,
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| 11 |
Current Status of an International Co-Operative Research Program, PARTRIDGE (Probabilistic Analysis as a Regulatory Tool for Risk-Informed Decision GuidancE)
Kim, Sun Hye;Park, Jung Soon;Kim, Jin Su;Lee, Jin Ho;Yun, Eun Sub;Yang, Jun Seog;Lee, Jae Gon;Park, Hong Sun;Oh, Young Jin;Kang, Sun Yeh;Yoon, Ki Seok;Park, Jai Hak;
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Korean Society of Pressure Vessels and Piping
, v.9, no.1, pp.62-69,
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| 12 |
A Simple Finite Element Modeling Method for Leak-Before-Break Crack Analysis of Pipe with Overlay Dissimilar Metal Weldments
Kim, Maan Won;Park, Young Sup;
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Korean Society of Pressure Vessels and Piping
, v.9, no.1, pp.70-76,
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