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) | 3D Analysis of Cooling Performance with Loss of Offsite Power Using GOTIHIC Code | Kyemin Oh and Gyunyoung Heo(KHU) Insik Na(ACT Co., Ltd.) Yujung Choi(KHNP) | PDF보기 | - | ||
| 2010-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Fretting Wear Experiments between the Same Alloy 690 Materials for Conservative Wear Evaluation of Steam Generator Tube | Jeong-Keun Lee and Chi-Yong Park(KEPRI) | PDF보기 | - | ||
| 2010-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Establishment of Advanced Technique for the Prediction of pH in the Sump Solution | Hee Cheol Kim and Sang-Nyung Kim(KHU) | PDF보기 | - | ||
| 2010-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Development of Generalized Correlation Equation for the Lacal Wall Shear Stress | Yu Mi Jeon, Jun Ho Bae, and Joo Hwan Park(KAERI) | PDF보기 | - | ||
| 2010-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Experimental Validation of the PRHRS Model in the TASS/SMR-S Code | Kyungmin Kang, Soo Hyung Yang, Young-Jong Chung, and Won-Jae Lee(KAERI) | PDF보기 | - | ||
| 2010-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Preliminary CFD Analyses on Debris Transport to ECCS Sump in Recirculation Mode for CANDU Type Plant, in Korea | Byung Il KWON, Jong Uk KIM, and Jae Seon CHO(FNC Tech.,) Tae Keun PARK(KOPEC) Sang Won LEE and Hyeon | PDF보기 | - | ||
| 2010-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | The Prediction of TASS/SMR-S Code for the Natural Circulation at VISTA Facility | InJoon Hwang, Soo-Hyung Yang, Soo-Hyung Kim, Young-Jong Chung, and Won-Jae Lee(KAERI) | PDF보기 | - | ||
| 2010-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Discharged Mass and Enthalpy in LOCA for CANDU NPP | Kim Yun Ho and Choi Hoon(KEPRI) | PDF보기 | - | ||
| 2010-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | A Comparision on Application of MARS and RELAP5 to KINS Realistic Evaluation Methodology | Byung Gil Huh, Dong Gu Kang, Deog-Yeon Oh, Young Seok Bang, and Sweng Woong Woo(KINS) | PDF보기 | - | ||
| 2010-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Study on Optimized Safety System Modeling for Small-scale Passive Reactor | Yun Sik Sung, Sung Won Lim, Yong Won Choi, and Un Chul Lee(SNU) | PDF보기 | - | ||
| 2010-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Analysis on Critical Heat Flux under Heaving Condition in Marine Reactor Using RETRAN-3D/INT | Min-Hee Kim and Goon-Cherl Park(SNU) | PDF보기 | - | ||
| 2010-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Conceptional Design about the Passive Containment Cooling System using Multi-pod Heat pipe | Seung-Won Han and Sang-Nyung Kim(KHU) | PDF보기 | - | ||
| 2010-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Feasibility Study on the Rod Ejection Simulation with Point Kinetics Model | Chansu Jang, Jungwon Sun, and Kilsup Um(KNF) | PDF보기 | - | ||
| 2010-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | PCTRAN/KSNP1000-A PC-Based Simulator for KSNP1000 | Li-Chi Cliff Po(MST) Juyoul Kim(FNC Tech.) | PDF보기 | - | ||
| 2010-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Post-Test Analysis of PKL G3.1 Test using MARS-KS | Seung Wook Lee and Bub Dong Chung(KAERI) | PDF보기 | - |
Last Modified : 1998-Autumn
