학술발표회 논문집
| Year | Div | Date/Time | ROOM | Title | Author | Abstract File | Presentation File |
|---|---|---|---|---|---|---|---|
| 2010-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Analytical Prediction of Turbulent Friction Factor for a Subchannel Consisting of a Rod Bundle | Jun Ho Bae and Joo-Hwan Park(KAERI) | PDF보기 | - | ||
| 2010-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Preliminary Analysis for the SMART Over-Pressure Protection | Sook Kwan Kim and Suk Ku Sim(En2t Inc.,) Suhn Choi and Kyoo Hwan Bae(KAERI) | PDF보기 | - | ||
| 2010-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Preliminary Analysis for the SMART LTOP(Low Temperature Over-Pressure Protection) | Sook Kwan Kim and Suk Ku Sim(En2t Inc.,) Suhn Choi and Kyoo Hwan Bae(KAERI) | PDF보기 | - | ||
| 2010-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Preliminary System Response Analysis of Rod Ejection Accident for APR1000 | Yo-Han Kim and Sang-Jun Ha(KEPRI) | PDF보기 | - | ||
| 2010-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Analysis of the SMART's Increased Heat Removal Transients by the Secondary System | In Sub Jun, Soo Hyoung Kim, Kyoo Hwan Bae, and Suhn Choi(KAERI) | PDF보기 | - | ||
| 2010-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Evaluation of Safety Margin for OPR1000 LBLOCA According to the Guidance of SMAP of NEA/CSNI | Soon Joon Hong, Su Hyun Hwang, Seong Soo Jeon, and Byung Chul Lee(FNC Tech.) Ju Yeop Park(KINS) | PDF보기 | - | ||
| 2010-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Accuracy Improvement of SPACE Code Using the Optimization for CHF Subroutine | Chang-Keun Yang, Yo-Han Kim, Jong-Eun Park, and Sang-Jun Ha(KEPRI) | PDF보기 | - | ||
| 2010-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Development and Validation of Pressure Tube Deformation and Subcooled Boiling Models of the MARS Code for Safety Analyses of the Wolsong NPP's | Churl Yoon and Bub Dong Chung(KAERI) Seunghoon Ahn(KINS) | PDF보기 | - | ||
| 2010-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Similarity Analysis of the VISTA Thermal-Hydraulic Integral Test Loop for a SmallBreak LOCA of the SMART Design | Hyun-Sik Park, Rae-Joon Park, Sang-Ki Moon, Hwang Bae, and Sung-Jae Yi(KAERI) Doo-Hyuk Kang and Jae- | PDF보기 | - | ||
| 2010-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Performance Evaluation of Annular Fuel in OPR-1000 Plant During a Main Steam Line Break Accident | Hyoung Tae Kim, Kyoo Hwan Bae, Tae Hyun Chun, and Wang Kee In(KAERI) | PDF보기 | - | ||
| 2010-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Sensitivity Studies on a 100% Break of the DVI Nozzle of ATLAS using MARS Code | Seyun Kim, Bum-Soo Youn, and Sang-Jun Ha(KEPRI) | PDF보기 | - | ||
| 2010-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Moderator Circulation Simulation for 35% Reactor Inlet Header Break in the Wolsong Nuclear Power Plant | Hyoung Tae Kim and Joo Hwan Park(KAERI) | PDF보기 | - | ||
| 2010-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Creep Rupture Analysis of Reactor Coolant System Boundary during a Total Loss of Feed Water Transient | Rae-Joon Park and Seong-Wan Hong(KAERI) | PDF보기 | - | ||
| 2010-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Preliminary Analysis of Severe Accident Progression Initiated from Small Break LOCA of a SMART Reactor | Youngho Jin, Jong-Hwa Park, and Dong-Ha Kim(KAERI) Seong-Won Cho(KORTIC) | PDF보기 | - | ||
| 2010-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Numerical Analysis of Molten Corium Dispersion during Hypothetical High-Pressure Accidents in APR1400 Nuclear Power Plant | Jongtae Kim, Kwang Soon Ha, Sang-Baik Kim, and Hee-dong Kim(KAERI) Jae-Sik Jeong(KOPEC) | PDF보기 | - |
Last Modified : 1998-Autumn
