-->

학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2007-Spring 제5분과 원자력안전 Thermal Conductivity Measurement and Heat Transfer Investigation of TiO2 and Al2O3 Nanofluids Shin Yoo, Jae Young Lee, and Man Woong Kim(HDU) PDF보기 -
2007-Spring 제5분과 원자력안전 Effects of the improved surface wettability and capillarity of nanoparticle deposition layer on CHF enhancement in pool boiling of nanofluids HyungDae Kim, MooHwan Kim(POSTECH) PDF보기 -
2007-Spring 제5분과 원자력안전 Development of Coupled Lattice Boltzmann and Finite Element Method for Fluid-Structure Interaction Problems in Commercial Nuclear Power Plants Kyung Wan Roh, Jong Chull Jo(KINS), and Young Kwon(NPS) PDF보기 -
2007-Spring 제5분과 원자력안전 Analysis of Flow-Induced Vibration Considering the Gap between Steam Generator Tube and Tube Support K. H. Lee, Y. J. Kim(GNEC), C. Y. Park(KAERI) PDF보기 -
2007-Spring 제5분과 원자력안전 Design Modification of Kori Unit 1 for the Equipment Qualification J.W. Park, M.Y. Kim, K.T. Han, J.D. Park(KOPEC) PDF보기 -
2007-Spring 제5분과 원자력안전 A Theoretical Method to Predict Wear of Plugged Tubes of Steam Generators Huinam Rhee(SNU), Ki-Wahn Ryu(CNU), Chi Yong Park(KEPRI) PDF보기 -
2007-Spring 제5분과 원자력안전 Study on the Dynamic Characteristics of the Fluid Loaded Structure Sungkeun Park, Do Hwan Lee, Shinchul Kang(KEPRI), Jangbom Chai, Yunchul Kim, Nakjin Jung(AJOU UNIV.) PDF보기 -
2007-Spring 제5분과 원자력안전 Capacity Evaluation of Penetration-Reinforcing Agent Jea-Myoung Noh, Myung Sug Cho, Young-Chul Song(KEPRI), Do-Gyum Kim(KICT) PDF보기 -
2007-Spring 제5분과 원자력안전 An Improved Seismic PRA Method for a Korean NPP Site Min Kyu Kim, Young Sun Choun, In Kil Choi(KAERI), Yasuki Ohtori(CRIEPI) PDF보기 -
2007-Spring 제5분과 원자력안전 Experimental investigation for the Secondary Failure Behavior of Partial Wall-Base Juncture Model in 1/4 PCCV K. W. Kim, N. S. Cho(HDEC), Y. S. Choun(KAERI) PDF보기 -
2007-Spring 제5분과 원자력안전 Analysis of Prestressed Concrete Containment Vessel(PCCV) under Severe Accident Loading Sang Hoon Noh, Jong Bo Lee and Jong Hak Kim(KHNP), Il Hwan Moon(KOPEC) PDF보기 -
2007-Spring 제5분과 원자력안전 Validation of a Steam Generator Heat Transfer Model for the TASS/SMR Code S.H. YANG, S.H. Kim, Y.J. Chung, S.K. ZEE(KAERI) PDF보기 -
2007-Spring 제5분과 원자력안전 Thermal Stress Evaluation for Pressurizer Spray Piping for NPP Dong Soo Song(KEPRI), Wan Jung Song(ENERGEO) PDF보기 -
2007-Spring 제5분과 원자력안전 Preliminary Numerical Evaluation of Measurement Method for a Time-Averaged Multi-Dimensional Bubble Velocity by Using a Multi-Sensor Probe D.J.Euh, B.J.Yun. C.H.Song(KAERI) PDF보기 -
2007-Spring 제5분과 원자력안전 A CFD Modeling Study for the Design of an Advanced HANARO Reactor Core Structure Jong-Hark Park, Hee-Teak Chae, Cheol Park, Heonil Kim(KAERI) PDF보기 -
Last Modified : 1998-Autumn