학술발표회 논문집
| Year | Div | Date/Time | ROOM | Title | Author | Abstract File | Presentation File |
|---|---|---|---|---|---|---|---|
| 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 | - | ||
| 2006-Spring | 제5분과 원자력안전-안전현안 | Analysis of Critical Flow Test Results for the Simulation of Loss of Coolant Accidents | C. K. Park, H. S. Park, Y. J. Yoon, and C. H. Song (KAERI) | PDF보기 | - | ||
| 2006-Spring | 제5분과 원자력안전-안전현안 | System Response Analysis of LOCV for APR1400 Using KNAP | Yo-Han Kim, Chang-Kyung Sung, and Hwan-Yong Jun (KEPRI) | PDF보기 | - | ||
| 2006-Spring | 제5분과 원자력안전-안전현안 | The Analysis of Control Rod Drop Accident for APR1400 Using KNAP | Chang-Keun Yang, Yo-Han Kim, and Chang-Kyung Sung (KEPRI) | PDF보기 | - | ||
| 2006-Spring | 제5분과 원자력안전-안전현안 | Flow Distribution in the Curved Narrow Channels of a Tubular Fuel | Jonghark Park, Heetaek Chae, Cheol Park, and Heonil Kim (KAERI) | PDF보기 | - |
Last Modified : 1998-Autumn
