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학술발표회 논문집 (ISSN: 3140-1864)

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2006-Spring 제5분과 원자력안전-안전현안 A Simulation of Aerosol Flow in the Model of the Gas Transport System of NPP Gag-Hyeon Ha and Jong-Jooh Kwon (KEPRI) PDF보기 -
2006-Spring 제5분과 원자력안전-안전현안 An Application of a Monte-carlo Method to Assess the Code Uncertainty of MARS Code on the Clad Temperature of FLECHT-SEASET 31504 Young Jin Lee and Bub-Dong Chung (KAERI) PDF보기 -
2006-Spring 제5분과 원자력안전-안전현안 CFD Analysis for the Steady State of a Postblowdown Experiment Hyung Seok Kang, Bo Wook Rhee, and Joo Hwan Park (KAERI) PDF보기 -
2006-Spring 제5분과 원자력안전-안전현안 Pressure Effects on Critical Heat Flux in Rod Bundles Dae-Hyun Hwang, Keung-Koo Kim, and Chung-Chan Lee (KAERI) PDF보기 -
2006-Spring 제5분과 원자력안전-안전현안 Sensitivity of the Absorption Coefficient of Radiation Medium on the CFX Simulation of the CS28-2 Experiment Hyung Tae Kim, Bo Wook Rhee, and Joo Hwan Park (KAERI) PDF보기 -
2006-Spring 제5분과 원자력안전-안전현안 A Study on the Thermal Radiation Heat Transfer in the CO2 Annulus of CANDU-6 Fuel Channel Under Post-blowdown Phase of LBLOCA Bo Wook Rhee, Hyung Tae Kim, H. S. Kang, and Joo Hwan Park (KAERI) PDF보기 -
2006-Spring 제5분과 원자력안전-안전현안 Validation of a CFD Code for Unsteady Flows with Cyclic boundary Conditions Jongtae Kim, Sang-Baik Kim, and Won-Jae Lee (KAERI) PDF보기 -
2006-Spring 제5분과 원자력안전-안전현안 Small Break LOCA Analysis for Kori 1 in Operation Mode 3 and 4 Hong, Soon-Joon and Lee, Byung-Chul (FNC) PDF보기 -
2006-Spring 제5분과 원자력안전-안전현안 Improvement of the NSSS T/H Module ARTS for Enhancing the Simulation Fidelity of YGN #1/2 Simulator In Young Seo, Myung Soo Lee, and Yong Kwan Lee (KEPRI) Jae Seung Suh (ENESYS) Gyoo Dong Jeun (HYU) PDF보기 -
2006-Spring 제5분과 원자력안전-안전현안 A CFD Analysis of the HANARO Irradiation Test Rigs for DUPIC Mini-elements Churl Yoon, Joo Hwan Park, Kwon Ho Kang, and Kee Chan Song (KAERI) PDF보기 -
2006-Spring 제5분과 원자력안전-안전현안 Development of the T/H Model for Aged Core in Wolsong-1 NPP Kim Yun Ho, Choi Hoon, and Kim Yong Bae (KEPRI) PDF보기 -
2006-Spring 제5분과 원자력안전-안전현안 Comparative Evaluation of Realistic and Deterministic Approach for Secondary System Piping Break Accidents Cheol Shin Lee, Shin Whan Kim, and Jong Tae Seo (KOPEC) PDF보기 -
2006-Spring 제5분과 원자력안전-안전현안 Assessment of a Cryogenic Cooling System Malfunctioning Accident in a CNS Jonghark Park and Kyehong Lee (KAERI) Donggil Hwang (Decon Eng.) PDF보기 -
2006-Spring 제5분과 원자력안전-안전현안 Modular Feedwater and Steam Lines Heat Transfer Effect on the Thermal Performance of a Once Through Steam Generator Jae-Kwang Seo, Han-Ok Kang, Young-In Kim, Juhyeon Yoon, and Keung-Ku Kim (KAERI) PDF보기 -
2006-Spring 제5분과 원자력안전-안전현안 APR1400 Steam Generator Tube Rupture Accident Analysis Using KNAP Jae-Hwa Koh, Yo-Han Kim, Dong-Hyuk Lee, and Chang-Kyung Sung (KEPRI) PDF보기 -
Last Modified : 1998-Autumn