학술발표회 논문집
| Year | Div | Date/Time | ROOM | Title | Author | Abstract File | Presentation File |
|---|---|---|---|---|---|---|---|
| 2011-Autumn | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Assessment of Pressurizer Transients Using the SPACE Code | Dong-Hyuk Lee, Bum-Soo Youn, and Se-Yun Kim(KHNP) | PDF보기 | - | ||
| 2011-Autumn | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Non-LOCA Safety Analysis for the APR1OOO Preliminary Design | Yo-Han Kim, Chang Keun Yang, and Jae Hwa Koh(KHNP) | PDF보기 | - | ||
| 2011-Autumn | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Benchmark Simulation of Turbulent Flow through a Tube Bundle | G. H. Lee and S. W. Woo(KINS) | PDF보기 | - | ||
| 2011-Autumn | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Off-take Model of the SPACE Code and Its Validation | Myung Taek Oh, Chan Eok Park, and Jong Joo Sohn(KEPCO E&C) | PDF보기 | - | ||
| 2011-Autumn | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | CFD Analysis of Condensation and Two-phase Flow in PCHX of PAFS | Kwang Chu Kim, Ho Je Seong, and Hee Jin Ko(KEPCO E&C) Choengryul Choi(ELSOLTEC) | PDF보기 | - | ||
| 2011-Autumn | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Radionuclide Release after LBLOCA with Loss of Class IV Power Accident in CANDU-6 Plant | Hoon Choi(KHNP) | PDF보기 | - | ||
| 2011-Autumn | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Safety Assessment of Void Increase in Reactor Coolant System Induced by LOP/SLB | Kun Ho Chun, Tae Young Choi, Young Koo Kim, and Choon Ho Park(KEPCO NF) | PDF보기 | - | ||
| 2011-Autumn | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Assessment of Condensation Models in SPACE in the Presence of Noncondensable Gas | Ji-Hun Kim, Jin-Hwa Yang, and Goon-Cherl Park(SNU) | PDF보기 | - | ||
| 2011-Autumn | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Assessment of MARS-KS Codes on LBLOCA for CANDU Type Reactor | Jin-Hyuck Kim, Joo-Sung Kim, and Kwang-Won Seul(KINS) | PDF보기 | - | ||
| 2011-Autumn | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Development of CANDU-6 Moderator System Safety Analysis Model Using the CATHENA Code | Jonghyun Kim and Dongsik Jin(ACT Co., Ltd) Dongwook Kho(KHNP) | PDF보기 | - | ||
| 2011-Autumn | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Experimental Study of Head Loss Induced by LOCA-generated Fiberglass Debris at New Type of ECCS Sump Screen | Jong Uk KIM, Byung Il KWON, and Jae Seon CHO(FNC Tech.) Tae Hyub HONG and Sang Won LEE(KHNP) | PDF보기 | - | ||
| 2011-Autumn | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Thermal Hydraulic Analysis of Flow nversion in a Research Reactor with Downward Core Cooling | Daeseong Jo, Jonghark Park, and Heetaek Chae(KAERI) | PDF보기 | - | ||
| 2011-Autumn | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Laminar Thermal-hydraulic Analysis for a PWR Fuel Assembly | Dong-Hyeog Yoon, Han-Chul Kim, and Kwang-Won Seul(KINS) | PDF보기 | - | ||
| 2011-Autumn | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Study on Quantification Method of the Uncertainties of Ageing Elements for Evaluation of the Effects of Ageing on Safety Margins during LBLOCA for CANDU Reactors | Yong Won Choi, In Young Kim, and Un Chul Lee(SNU) Kab Kim(KINS) | PDF보기 | - | ||
| 2011-Autumn | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Discussion on the Development of Numerical Analysis Based on Staggered Grid for Arbitrary 3-dimensional Mesh Shape | Soon Joon HONG and Yeon Joon CHOO(FNC Tech.) Tae Young HAN(KAERI) | PDF보기 | - |
Last Modified : 1998-Autumn
