학술발표회 논문집
| Year | Div | Date/Time | ROOM | Title | Author | Abstract File | Presentation File |
|---|---|---|---|---|---|---|---|
| 2012-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Conversion of Chord Length Data into Bubble Size Distribution: Generation of Chord Length Data and the Methodology Comparison | Hoang Nhan Hien, D.J .Euh, and C-H. Song(KAERI) B.J .Yun(PNU) | PDF보기 | - | ||
| 2012-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Design Modification of Boron Injection Tank for a Westinghouse Type NPP | Dong Soo Song(KHNP CRI) Song Kee Sung and Jae Il Lee(KEPCO NF) | PDF보기 | - | ||
| 2012-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Development of an Automatic Verification Program for Thermal-hydraulic System Codes | J. Y. Lee, K. T. Ahn, S. H. Ko, Y. S. Kim, D. W. Kim, and J. J. Jeong(PNU) J. S. suh and Y. S. Cho(S | PDF보기 | - | ||
| 2012-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Assessment of SPACE Code Using the LSTF 10% MSLB Test | Yo-Han Kim, Chang Keun Yang, and Sang Jun Ha(KHNP CRI) | PDF보기 | - | ||
| 2012-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Evaluation of Natural Circulation Cooldown for the SMART | Sook Kwan Kim, Koo Sam Kim, and Suk Ku Sim(en2t) Ju Yeop Park and Kwang Won Seol(KINS) Kyu Hwan Bae( | PDF보기 | - | ||
| 2012-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | The Characteristics of Single Stage and Multi Stage Core DNBR Analysis Models | Younhwa Lee and Joon Hyong Cho(KEPCO NF) | PDF보기 | - | ||
| 2012-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Magnetite Transport Characteristics in a CANDU Reactor | Jun Ho Bae, Bo Wook Lee, and Jong Yeob Jeong(KAERI) | PDF보기 | - | ||
| 2012-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Fluid to Fluid Modeling of R134a CHF in SMART 5x5 Rod Bundles | Seong Jin Kim, Jeong Hun Cha, Kyong Won Seo, Hyuk Kwon, and Dae Hyun Hwang(KAERI) | PDF보기 | - | ||
| 2012-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Sensitivity Study of Regional TDC in MATRA-S Code Using PSBT Benchmark Exercise | Seong Jin Kim, Jeong Hun Cha, Kyong Won Seo, Hyuk Kwon, and Dae Hyun Hwang(KAERI) | PDF보기 | - | ||
| 2012-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Validation of iSAM Using the Plant Startup Test | Chansu. Jang and Kilsup. Um(KEPCO NF) | PDF보기 | - | ||
| 2012-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | OPR1000 Control Rod Drop Accident Simulation Using the SPACE Code | Chang-Keun Yang, Sang-Jun Ha, and Chan-Kook Moon(KHNP CRI) | PDF보기 | - | ||
| 2012-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Simulation of High Pressure Steam Boosting for Functional Test of Nuclear Equipment | Sangho Sohn, Jin Wook Ko, Kyung Ha Ryu, and Byung Duck Kim(KIMM) | PDF보기 | - | ||
| 2012-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Analysis of ATLAS Cold Leg SBLOCA Using SPACE Code | Doo-Hyuk Kang and Jae-Seung Suh(Sen Tech) Seyun Kim(KHNP CRI) | PDF보기 | - | ||
| 2012-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Preliminary Validation and Verification of TURBO_DESIGN for S-CO2 Axial Compressor | Jekyoung Lee, Jeong Ik Lee, Yoonhan Ahn, and Seong Gu Kim(KAIST) Ho Joon Yoon and Yacine Addad(KUSTA | PDF보기 | - | ||
| 2012-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Example Calculations of In_vessel Steam Explosions for a Prototypical PWR | Ik Kyu Park and Seong Wan Hong(KAERI) | PDF보기 | - |
Last Modified : 1998-Autumn
