-->

학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2007-Spring 제5분과 원자력안전 Development of Web-Based Plant Reliability Information System (PRinS) Seok-Won Hwang, Myoung-Su Kim, Young-Seung Kim(KHNP) PDF보기 -
2007-Spring 제5분과 원자력안전 A Study on State-of-the-Art Technology for Common Cause Failures Analysis and Suggestions Seok-Won Hwang(KHNP), Ho-June Jeon(HEC), Keun-Sung Lee, Eun-Chan Lee(KHNP) PDF보기 -
2007-Spring 제5분과 원자력안전 Effects of Forgetting Phenomenon on Surveillance Test Interval Ho-Joong Lee and Seung-Cheol Jang(KAERI) PDF보기 -
2007-Spring 제5분과 원자력안전 Transient Initiating Event Analysis for Nuclear Power Plants in Korea Park, Jin-Hee, Han, Sang-Hoon(KAERI) PDF보기 -
2007-Spring 제5분과 원자력안전 Stress Corrosion Cracking of Steam Generator Tubing in a 0.01 M NaHS Solution E. H. Lee, K. M. Kim, W. Y. Maeng(KAERI) PDF보기 -
2007-Spring 제5분과 원자력안전 Numerical Analysis of Liquid Metal Cooled Rod Assembly Hyoung M. Son, Kune Y. Suh(SNU) PDF보기 -
2007-Spring 제5분과 원자력안전 Performance Tests of Locking Devices and a Prototype Fabrication of an AHR Fuel Assembly Jeong-Soo Ryu, Yeong-Garp Cho, Jung-Hee Lee, Cheol Park(KAERI) PDF보기 -
2007-Spring 제5분과 원자력안전 Measurement of Physical Clearance for SOR/CAR Movement in HANARO Yeong-Garp Cho, Jin-Won Shin, Jung-Hee Lee and Hoan-Sung Jung(KAERI) PDF보기 -
2007-Spring 제5분과 원자력안전 Effect on the HANARO CNS under a HRS Malfunction Jungwoon Choi, Dong-gil Hwang, Kye Hong Lee, and Hark Rho Kim(KAERI) PDF보기 -
2007-Spring 제5분과 원자력안전 Evaluation for RCS Leak Detection Capability to Apply LBB Concept to Main Loop Piping for Yonggwang Units 1 and 2 S.J. Yune, S.K. Suh, Y.S Sul, I.Y. Kim(KOPEC), K.Y. Cho(KHNP) PDF보기 -
2007-Spring 제5분과 원자력안전 3D Fatigue Analysis for the Steam Generator Economizer Feedwater Nozzle of the Advanced Reactor Taesoon Kim, Byongsup Kim(KHNP), Kwanghan Lee(GNEC) PDF보기 -
2007-Spring 제5분과 원자력안전 Nano-TiO2 Penetration into a Tubesheet Crevice of a Steam Generator Jung Won Na(KAERI), Jong Hwan Kim(STU), Uh Chul Kim, Wan Young Maeng(KAERI) PDF보기 -
2007-Spring 제5분과 원자력안전 Nondestructive Method Evaluating Aging of Cable in Nuclear Power Plants by Ultrasonic Wave Hyunsub Kim, Changdae Park, Chisung Song(KIMM) PDF보기 -
2007-Spring 제5분과 원자력안전 Transient Moderator Simulation Using CFX10-CAMO, a CANDU Moderator Analysis Model Based on a Coupled Solver Churl Yoon and Joo Hwan Park(KAERI) PDF보기 -
2007-Spring 제5분과 원자력안전 CFX Simulation of High Temperature Thermal-Chemical Experiment: CS28-2 Hyoung Tae Kim, Bo Wook Rhee, Joo Hwan Park(KAERI) PDF보기 -
Last Modified : 1998-Autumn