학술발표회 논문집
| Year | Div | Date/Time | ROOM | Title | Author | Abstract File | Presentation File |
|---|---|---|---|---|---|---|---|
| 2010-Autumn | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Separate Effect Test Assessment about Interfacial Heat Transfer Model and Correlations in SPACE Code | Sung Won Bae, Seung Wook Lee, and Kyung Du Kim(KAERI) | PDF보기 | - | ||
| 2010-Autumn | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Evaluation of Inadvertent PRHRS Operation for REX-10 | Sung Won Lim, Young Jong Chung, and Won Jae Lee(KAERI) Yeon Gun Lee(SNU) | PDF보기 | - | ||
| 2010-Autumn | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Analysis of Heat Load to Moderator in Large LOCA for CANDU NPP | Kim Yun Ho(KEPCO RI) | PDF보기 | - | ||
| 2010-Autumn | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Study on Calculation of Uncertainty and Range of Ageing Elements Using Measured Data of Fuel Channel Flow Rate | Yong Won Choi, In Young Kim, and Un Chul Lee(SNU) Kap Kim(KINS) | PDF보기 | - | ||
| 2010-Autumn | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | The Regeneration of Environmental Qualification Test Envelope for 3-Loop Westinghouse Type NPP | Dong Soo Song(KEPCO RI) | PDF보기 | - | ||
| 2010-Autumn | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Radionuclide Release after End Fitting Failure Accident in CANDU-6 Plant | Hoon Choi, Yun-ho Kim, and Kwang-ho Lee(KEPCO RI) | PDF보기 | - | ||
| 2010-Autumn | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | The Preliminary Study for Numerical Computation of 37 Rod Bundle in CANDU Reactor | Yu Mi Jeon, Jun Ho Bae, and Joo Hwan Park(KAERI) | PDF보기 | - | ||
| 2010-Autumn | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Analysis of pH on Water Temperature in the Recirculation Sump | Sang Nyung Kim and Hyoung Ju Yoon(KHU) | PDF보기 | - | ||
| 2010-Autumn | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Development of Fast Running DNBR Code | Hyuk Kwon, K.W. Seo, S.J. Kim, and D.H. Hwang(KAERI) | PDF보기 | - | ||
| 2010-Autumn | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Steam Generator Heat Transfer Model Validation in TASS/SMR-S Code Using MRX Experimental Results | Kyungmin Kang, Soo Hyung Yang, Young-Jong Chung, and Won-Jae Lee(KAERI) | PDF보기 | - | ||
| 2010-Autumn | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Case Study of MATRA-S for PNL 7x7 Rod Bundle Blockage- II. CFD Analysis | Seong Jin Kim, Kyong Won Seo, Tae Woo Kim, Jeong Hun Cha, Hyuk Kwon, and Dae Hyun Hwang(KAERI) | PDF보기 | - | ||
| 2010-Autumn | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Simulation of MIT Pressurizer Experiment Using SPACE Code | Dong Hyuk Lee, Yo Han Kim, Chang Keun Yang, Seyun Kim, Bum Soo Youn, and Sang Jun Ha(KEPCO RI) | PDF보기 | - | ||
| 2010-Autumn | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | A Simple in-surge Pressure Analysis Using the SPACE Code | Bum Soo Youn, Yo Han Kim, Dong-Hyuk Lee, Chang Keun Yang, Se-Yun Kim, and Sang Jun Ha(KEPCO RI) | PDF보기 | - | ||
| 2010-Autumn | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | CEA Ejection Accident Analysis for APR1000 | Yo-Han Kim and Sang Jun Ha(KEPCO RI) | PDF보기 | - | ||
| 2010-Autumn | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Assessment of Turbulence Models for Isothermal Vertical-upward Bubbly Flows | V.T. Nguyen, B.J. Yun, and C.H. Song(UST) B.U. Bae, and D.J. EuhKAERI) | PDF보기 | - |
Last Modified : 1998-Autumn
