학술발표회 논문집
| Year | Div | Date/Time | ROOM | Title | Author | Abstract File | Presentation File |
|---|---|---|---|---|---|---|---|
| 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 | - | ||
| 2010-Autumn | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Simulations of Two-phase Flows in Adiabatic Pipes Using SPACE Code | Byoung Jae Kim, Moon Kyu Hwang, Kyoung Doo Kim, and Seung Wook Lee(KAERI) | PDF보기 | - | ||
| 2010-Autumn | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Component Model for Reactor Coolant Pumps in SPACE Code | Byoung Jae Kim and Kyoung Doo Kim(KAERI) | PDF보기 | - | ||
| 2010-Autumn | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Preliminary Assessment of the KAERI 6x6 Reflood Experiment for the SPACE Code Using General Wall Heat Transfer Models | Sang-Ki Moon, Jungwoo Kim, Kyung-Doo Kim, Ki-Yong Choi, Hyun-Sik Park, and Seok Cho(KAERI) | PDF보기 | - | ||
| 2010-Autumn | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Evaluating the Break Flow for the 100% DVI Line Break Accident of ATLAS Using the RELAP5/MOD3.3 Code | Suk-Ho Lee, Sung-Chang You, and Han-Gon Kim(KHNP) | PDF보기 | - | ||
| 2010-Autumn | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Case Study of MATRA-S for PNL 7x7 Rod Bundle Blockage Test - I. Subchannel Analysis | Kyong-Won Seo and Dae-Hyun Hwang(KAERI) | PDF보기 | - |
Last Modified : 1998-Autumn
