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) | 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 | - |
| 2023-Spring | 5H : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.18(Thu) 13:00 | Lobby (3F) | Sensitivity Study for Active Single Failure in the Intermediate Break LOCA | Yerim Park, Seyun Kim, and Junkyu Song(KHNP) | PDF보기 | - |
| 2023-Spring | 5H : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.18(Thu) 13:00 | Lobby (3F) | Numerical Modeling of Flow Boiling in a Rectangular channel using OpenFOAM | Iljin Kim and Hyungdae Kim(KHU) | PDF보기 | PPT보기 |
| 2023-Spring | 5I : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.18(Thu) 13:00 | Lobby (3F) | A Preliminary Study on Reliability Evaluation Methodology for Passive Safety Systems | Youngjae Park, Jeehee Lee, and Seong-Su Jeon(FNC Tech.), Ju-Yeop Park(KINS) | PDF보기 | - |
| 2023-Spring | 5I : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.18(Thu) 13:00 | Lobby (3F) | Modeling the CRUD Effects on Heat Transfer in Subchannels of Pressurized Water Reactor | Hyeon Ji Kim, Ji Yong Kim, and In Cheol Bang(UNIST) | PDF보기 | - |
| 2023-Spring | 5I : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.18(Thu) 13:00 | Lobby (3F) | Preliminary Analysis of PIUS-type Experimental Apparatus with Hot/Cold Fluids Interface for Inherently Safety | Ju Hun Jung and In Cheol Bang(UNIST) | PDF보기 | - |
| 2023-Spring | 5I : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.18(Thu) 13:00 | Lobby (3F) | Safety Analysis of MicroURANUS LFR for Unprotected Loss of Flow and Unprotected Loss of Heat Sink | Joo Hyung Seo and In Cheol Bang(UNIST) | PDF보기 | - |
Last Modified : 1998-Autumn