학술발표회 논문집
| Year | Div | Date/Time | ROOM | Title | Author | Abstract File | Presentation File |
|---|---|---|---|---|---|---|---|
| 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 | - | ||
| 2010-Autumn | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Core Heat Transfer Model Validation of the TASS/SMR-S Code Using the Bennett s Test | In Sub Jun, Kyu Hwan Bae, Young Jong Chung, and Won Jae Lee(KAERI) In Sik Na(ACT Co., Ltd.) | PDF보기 | - | ||
| 2010-Autumn | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | SPACE Code Development and Assessment Plans | Chang-Keun Yang, Dong-Hyuk Lee, Yo-Han Kim, and Sang-Jun Ha(KEPCO RI) | PDF보기 | - | ||
| 2010-Autumn | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Verification of the Core Side Pressure Drop Calculation Sub-routine | Jeong-hun Cha, Kyong-Won Seo, Hyuk Kwon, Teawoo Kim, and Dae-Hyun Hwang(KAERI) | PDF보기 | - | ||
| 2010-Autumn | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | An ATWS Analysis with a Realistic Evaluation Methodology | Min Shin Jung, Gyu Cheon Lee, and Eun Kee Kim(KEPCO E&C) | PDF보기 | - | ||
| 2010-Autumn | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Gap Conductance Model Validation in the TASS/SMR-S Code Using MARS Code | Sang-Jun Ahn, Soo Hyung Yang, Young-Jong Chung, and Won-Jae Lee(KAERI) | 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) | Preparation of Input Deck Using MULTID Component to Model 3-dimensional Reactor Pressure Vessel for KORI 3&4 | Doo-Hyuk Kang, Jae-Seung Suh, Kyung-Chul Seo, Yeon-Sik Cho, and Ji-Hoon Park(SENTECH) Seung-Hoon Ahn | PDF보기 | - | ||
| 2010-Autumn | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Thermalhydraulic Response of CANDU6 in the End Fitting Failure Event | Kwangho Lee and Hoon Choi(KEPCO RI) | PDF보기 | - | ||
| 2010-Autumn | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Preliminary Assessment of the Reflood Heat Transfer Models for the SPACE Code | Jungwoo Kim, Sang-Ki Moon, Ki-Yong Choi, Hyun-Sik Park, and Kyung-Doo Kim(KAERI) | PDF보기 | - | ||
| 2010-Autumn | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Detached-Eddy Simulation of a Fluidic Device for a Prediction of Pressure Loss Characteristics in a Low Flow Mode | Sang-Gyu Lim, Suk-Ho Lee, and Han-Gon Kim(KHNP) | PDF보기 | - |
Last Modified : 1998-Autumn
