학술발표회 논문집
| Year | Div | Date/Time | ROOM | Title | Author | Abstract File | Presentation File |
|---|---|---|---|---|---|---|---|
| 2023-Spring | 5H : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.18(Thu) 13:00 | Lobby (3F) | GAMMA+ Code Verification for Natural Circulation Phenomena in a MSR System | SUNG NAM Lee, Nam-il Tak, Hong-Sik Lim, and Sang Ji Kim(KAERI) | PDF보기 | - |
| 2023-Spring | 5H : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.18(Thu) 13:00 | Lobby (3F) | Simulation of a Linear Quadratic Regulator Controller for sCO2 Cycle Using MARS-KS | Gi Hyeon Kim and Jeong Ik Lee(KAIST) | PDF보기 | - |
| 2023-Spring | 5H : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.18(Thu) 13:00 | Lobby (3F) | Simulation of IBLOCA (Intermediate-break Loss of a Coolant Accident) Scenario of PKL i2.2 Test | Jong Hyuk Lee and Seung Wook Lee(KAERI) | PDF보기 | - |
| 2023-Spring | 5H : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.18(Thu) 13:00 | Lobby (3F) | Evaluation of the Increase in Feedwater Accident with Common Cause Failure during Flexible Operation using SPACE Code | Hyoung Kyoun Ahn, In Ho Song, and Seok Jeong Park(KEPCO E&C), Lee Jae Min(KHNP CRI) | PDF보기 | - |
| 2023-Spring | 5H : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.18(Thu) 13:00 | Lobby (3F) | Study on Main Steam Line Break Induced Steam Generator Tube Rupture Accident using SPACE Code | MinJeong Kim, Chang-Keun Yang, and Seung-Chan LEE(KHNP) | PDF보기 | - |
| 2023-Spring | 5H : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.18(Thu) 13:00 | Lobby (3F) | Sensitivity Test for Intermediate Break Loss of Coolant of LSTF No.2 using SPACE | Chiwoong CHOI, Byung-hyun Yoo, and Seung-wook Lee(KAERI) | PDF보기 | - |
| 2023-Spring | 5H : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.18(Thu) 13:00 | Lobby (3F) | Preliminary CFD Analysis of Refrigerant Cooled, Scaled Down RPV of OPR1000 | Do Yeong Lim and In Cheol Bang(UNIST) | PDF보기 | - |
| 2023-Spring | 5H : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.18(Thu) 13:00 | Lobby (3F) | Prediction of Flow Instability of Natural Convection in Sloped Channel | Byeonghee Lee and Seok-Gyu Jeong(KAERI) | PDF보기 | - |
| 2023-Spring | 5H : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.18(Thu) 13:00 | Lobby (3F) | Analysis of CHF under Oscillatory Flow Condition using MARS-KS Moving Reactor Model | Moonhee Choi and Hyoung Kyu Cho(SNU) | PDF보기 | - |
| 2023-Spring | 5H : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.18(Thu) 13:00 | Lobby (3F) | Validation of a CFX Code for Helical-Type MHD Power Generator | Jong-Pil Park and Doo Hee Chang(KAERI) | PDF보기 | - |
| 2023-Spring | 5H : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.18(Thu) 13:00 | Lobby (3F) | CCP Assessment under CANDU Normal Operating Condition with Various Reactor Power | Jae Yong Oh, Euiseung Ryu, and Donghwan Park(KHNP) | PDF보기 | - |
| 2023-Spring | 5H : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.18(Thu) 13:00 | Lobby (3F) | Comparison of CCP using CHF Correlations under HSP-2 & 3 Conditions | Jae Yong Oh, Euiseung Ryu, and Donghwan Park(KHNP) | PDF보기 | - |
| 2023-Spring | 5H : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.18(Thu) 13:00 | Lobby (3F) | The Evaluation Process for Leak Detection Systems using CFD Analysis | Dae Kyung Choi, Won Man Park, Sung Man Son, and Choengryul Choi(Elsoltec), Woo-Shik Kim, Tae-Soon Kwon, and Dong-Jin Euh(KAERI) | PDF보기 | - |
| 2023-Spring | 5H : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.18(Thu) 13:00 | Lobby (3F) | A Numerical Study on Heat Transfer Characteristics of Various Shapes of Fuel Rods in Nuclear Reactors | Hyerim Woo, Sungjin Yang, and Jongrak Choi(KETI) | PDF보기 | - |
| 2023-Spring | 5H : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.18(Thu) 13:00 | Lobby (3F) | Development of CFD Simulation Methodology for Cladding Oxidation Phenomenon | Siwon Seo, Armanto Simanjuntak, Benrico Simamora, and Jaeyoung Lee(HGU) | PDF보기 | - |
Last Modified : 1998-Autumn
