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) | 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 | - |
| 2023-Spring | 5I : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.18(Thu) 13:00 | Lobby (3F) | Effects of Truly Optimized PWR Lattice Core Design on Reactor Power and Critical Heat Flux in a Natural Circulation Small Modular Reactor | Jae Hyung Park, Jihun Im, Hyo Jun An, and Sung Joong Kim(HYU) | PDF보기 | - |
| 2023-Spring | 5I : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.18(Thu) 13:00 | Lobby (3F) | Performance Comparison of Compact Heat Exchangers Suitable for Chloride Molten Salt Fast Reactor Intermediate Heat Transport System | Sunghyun Yoo, In Woo Son, Sungwook Choi, and Jeoing Ik Lee(KAIST) | PDF보기 | - |
| 2023-Spring | 5I : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.18(Thu) 13:00 | Lobby (3F) | Predictability Evaluation of SPACE for DVI Line Break Test with ATLAS | Hae Min Park, Sung Won Bae, and Seung Wook Lee(KAERI) | PDF보기 | - |
| 2023-Spring | 5I : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.18(Thu) 13:00 | Lobby (3F) | Performance Evaluation of an AHX for Thermal Energy Storage System Test Loop | In Sub Jun, Jung Yoon, and Hyeonil Kim(KAERI) | PDF보기 | - |
| 2023-Spring | 5I : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.18(Thu) 13:00 | Lobby (3F) | Preliminary Multi-Physcis Aanalysis of a 2x2 Rod Array Using CUPID/GIFT Coupled Code | Yeong Hun Lee, Kyuseok Sim, Youho Lee, and Hyoung Kyu Cho(SNU) | PDF보기 | - |
| 2023-Spring | 5I : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.18(Thu) 13:00 | Lobby (3F) | SB LOCA Analysis of a Floating Nuclear Reactor Under Combined Motion Condition | Yujeong Ko, and Hyoung Kyu Cho(SNU), Han Rim Choi(KEPCO E&C) | PDF보기 | - |
| 2023-Spring | 5I : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.18(Thu) 13:00 | Lobby (3F) | Evaluation the Effect of Surface Roughness of Cr-coated Cladding with Multi-layer Model on Large Break-Loss of Coolant Accident | Dong-Young Lee, Tae-Sun Ro, Bub-Dong Chung, and Soon-Joon Hong(FNC Tech.) | PDF보기 | - |
| 2023-Spring | 5I : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.18(Thu) 13:00 | Lobby (3F) | Preliminary Sensitivity Analysis of APR1400 IBLOCA Scenario using SPACE Code | Seung Wook LEE, ByungHyun YOU, and Jonghyuk LEE(KAERI) | PDF보기 | - |
| 2023-Spring | 5I : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.18(Thu) 13:00 | Lobby (3F) | Simulation of Recirculation between Reactor Coolant System and Containment with MARS-KS using Simple SMR Input | Jin-Hwa Yang, Byong Guk Jeon, and Hwang Bae(KAERI) | PDF보기 | - |
Last Modified : 1998-Autumn
