학술발표회 논문집
| Year | Div | Date/Time | ROOM | Title | Author | Abstract File | Presentation File |
|---|---|---|---|---|---|---|---|
| 2024-Autumn | 5B : 원자력열수력 (Nuclear Thermal Hydraulics) | 10.24(Thu) 09:20 | 600A | CFD Simulation for Predicting Core Inlet Flow Distribution in a 1/5 Scale Model of the APR1000 | Uiju Jeong and Yujung Choi(KHNP), Kihwan Kim and Dong-Jin Euh(KAERI) | PDF보기 | - |
| 2024-Autumn | 5B : 원자력열수력 (Nuclear Thermal Hydraulics) | 10.24(Thu) 09:40 | 600A | CFD Modeling and Simulation of Flow Pattern Transition in Subcooled Flow Boiling under High Void Fraction Conditions | Iljin Kim, In-Yeop Kang, Gubin Lee, and Hyungdea Kim(KHU) | PDF보기 | - |
| 2024-Autumn | 5B : 원자력열수력 (Nuclear Thermal Hydraulics) | 10.24(Thu) 10:00 | 600A | Improvement of Swarm Rise Region Modelling in SPARC-90 Pool Scrubbing Code | Erol Bicer, Yeon-Jun Choo, and Soon-Joon Hong(FNC Tech.) | PDF보기 | - |
| 2024-Autumn | 5B : 원자력열수력 (Nuclear Thermal Hydraulics) | 10.24(Thu) 10:20 | 600A | A Study on the Effects of Passive Auxiliary Feedwater System on Mass and Energy Release During A Postulated Main Steam Line Break Accident in APR1000 | Jisu Kim, Sung Yong Kim, Seong Ho Jee, Ye Eun An, Sang Jin Lee, Min Shin Jung, and Ung Soo Kim(KEPCO E&C) | PDF보기 | - |
| 2024-Autumn | 5B : 원자력열수력 (Nuclear Thermal Hydraulics) | 10.24(Thu) 11:00 | 600A | Thermal-hydraulic Analysis of The Cold Neutron Source Using CUPID Code | Minseok Choi and Jee He Lee(FNC Tech.), Han Young Yoon and Yun Je Cho(KAERI) | PDF보기 | - |
| 2024-Autumn | 5B : 원자력열수력 (Nuclear Thermal Hydraulics) | 10.24(Thu) 11:20 | 600A | Comparison of MARS-KS and SPACE Code for Modeling a Helical Steam Generator | Semin Joo, Doh Hyeon Kim, Seunghwan Oh, Jun Ha Hwang, and Jeong Ik Lee(KAIST) | PDF보기 | PPT보기 |
| 2024-Autumn | 5B : 원자력열수력 (Nuclear Thermal Hydraulics) | 10.24(Thu) 11:40 | 600A | Multiphysics Simulation of an Inadvertent Opening of a Steam Generator Atmospheric Dump Valve | Marek Kopecek and Aya Diab(KINGS) | PDF보기 | - |
| 2024-Autumn | 5B : 원자력열수력 (Nuclear Thermal Hydraulics) | 10.24(Thu) 12:00 | 600A | Machine Learning Prediction of Multiple Steam Generator Tube Rupture accident in APR1400 | Sonia Justyna Spisak and Aya Diab(KINGS) | PDF보기 | - |
| 2024-Autumn | 5C : 원자력열수력 (Nuclear Thermal Hydraulics) | 10.24(Thu) 13:20 | 600A | Integrated Development Environment of SPACE Problem Analysis | Chansu Jang(KEPCO NF) | PDF보기 | PPT보기 |
| 2024-Autumn | 5C : 원자력열수력 (Nuclear Thermal Hydraulics) | 10.24(Thu) 13:40 | 600A | Extension of MARS-KS Code Based Modeling Scheme, SEMICOM, to Predict the Dynamics of Combined Valve System in PECCS | Young Seok Bang, Youngjae Park, You Cho Choi, Seong-Su Jeon, and Soon-Jun Hong(FNC Tech.) | PDF보기 | - |
| 2024-Autumn | 5C : 원자력열수력 (Nuclear Thermal Hydraulics) | 10.24(Thu) 14:00 | 600A | Multiphysics Simulation of APR1400 Load Follow Operation | Ivan Panciak and Aya Diab(KINGS) | PDF보기 | - |
| 2024-Autumn | 5C : 원자력열수력 (Nuclear Thermal Hydraulics) | 10.24(Thu) 14:20 | 600A | Preliminary Performance Analysis on Passive Containment Cooling System of i-SMR Using MARS-KS | Seong-Su Jeon, Sang Gyun Nam, Youngjae Park, Jehee Lee, Jan Hrukovic, Soon-Joon Hong, and Bub Dong Chung(FNC Tech.) | PDF보기 | - |
| 2024-Autumn | 5C : 원자력열수력 (Nuclear Thermal Hydraulics) | 10.24(Thu) 14:40 | 600A | Impacts of Fuel Deformation on LOCA Safety : A Multi-Rod Modeling Approach | Joosuk Lee, Seulbeen Kim, Jang Keun Park, and Yongseok Choi(KINS) | PDF보기 | - |
| 2024-Autumn | 5C : 원자력열수력 (Nuclear Thermal Hydraulics) | 10.24(Thu) 15:00 | 600A | Recent Challenges in SMR Rod Bundle Critical Heat Flux Prediction | Nhan Hien Hoang and Seong-Su Jeon(FNC Tech.), Ju-Yeop Park(KINS) | PDF보기 | - |
| 2024-Autumn | 5D : 원자력열수력 (Nuclear Thermal Hydraulics) | 10.25(Fri) 09:00 | 607 | Enhancing Flow Control through Transformer-based Reinforcement Learning | Daehyung Lee and Hyun Sun Park(SNU), Joongoo Jeon(Jeonbuk National Univ.) | PDF보기 | - |
Last Modified : 1998-Autumn
