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학술발표회 논문집 (ISSN: 3140-1864)

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2010-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Study on LOCA Frequency and Contribution to Risk of Nuclear Power Plant Seong Soo Choi, Dong Sik Jin, and Poong Oh Kim(ACT Co.,Ltd.) Inn Seock Kim(ISSA Tech.) PDF보기 -
2010-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) A Study on the Regulatory Requirement of Event Frequency Change by Facility Improvement and Modification in Wolsong Unit 1 Kilyoo Kim and Jinhee Park(KAERI) PDF보기 -
2010-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Comparison between Heinrich's Law and the Number of Events in Domestic Nuclear Power Plants Sun Yeong Choi and Joon-Eon Yang(KAERI) PDF보기 -
2010-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Assessment of In-Core Damage for Feeder Stagnation Break in CANDU Jong Yeob Jung and Joo Hwan Park(KAERI) PDF보기 -
2010-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Analysis of Worldwide Regulatory Framework for On-Line Maintenance Sang-Kyu AHN, Kyu-Myung OH, and Chang-Ju Lee(KINS) PDF보기 -
2010-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Design of Nanoparticle Engineered Safety Injection Tank Myoung-suk Kang, Changhyun Jee, Sangjun Park, and Gyunyoung Heo(KHU) In Choel Bang(UNIST) PDF보기 -
2010-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Application of a New Approach for Estimating LOCA and SGTR Frequencies Ho-Jun Jeon, Ji-Yong Oh, and Moon-Goo Chi(KHNP) PDF보기 -
2010-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) An Evaluation of the Unexpected Trip Limits Using the Quality Control Approach Hyun-woo Lee and Moosung Jae(HYU) Kilyoo Kim(KAERI) PDF보기 -
2010-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Thermal Field of Moderator Circulation in CANDU-6 Reactor Tae Kwang Eom, Sung Je Hong, and Jae Young Lee(HGU) PDF보기 -
2010-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Evaluation of MARS Code on CHF with Fluid-to-Fluid Method Under Inlet Flow Fluctuation Jin S. Hwang, Jong W. Kim, and Goon C. Park(SNU) PDF보기 -
2010-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Simulation of UPTF Test 20 by Using MARS Multi-Dimensional Component Sung Won Bae and Bub Dong Chung(KAERI) PDF보기 -
2010-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Transport Characteristics of Representative Debris in a Open Channel Kyung Sik Choi and Ji Hwan Joeng(PNU) Joo Yeop Park(KINS) PDF보기 -
2010-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) MARS Transient Analyzer for Dual Reactor Unit Producing 2000 MWe Kyoung M. Kang and Kune Y. Suh(SNU) PDF보기 -
2010-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Experimental Validation of a Thermal-hydraulic Analysis Code for REX-10 Yeon-Gun Lee, Jong-Won Kim, and Goon-Cherl Park(SNU) PDF보기 -
2010-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Preliminary Test for Constitutive Models of CAP Yeon Joon Choo, Soon Joon Hong, Su Hyun Hwang, Keo Hyung Lee, Min Ki Kim, and Byung Chul Lee(FNC Tec PDF보기 -
Last Modified : 1998-Autumn