학술발표회 논문집
Year | Div | Date/Time | ROOM | Title | Author | Abstract File | Presentation File |
---|---|---|---|---|---|---|---|
2020-Autumn | 5A : 원자력열수력 (Nuclear Thermal Hydraulics) | 12.17(Thu) 11:20 | On-line | CHF Model Development for Subcooled Condition in Narrow Rectangular Channel | Jung Hyun Song, Jun Yeong Jung, and Yong Hoon Jeong(KAIST), Soon Heung Chang(HGU) | PDF보기 | - |
2020-Autumn | 5B : 원자력열수력 (Nuclear Thermal Hydraulics) | 12.17(Thu) 13:30 | On-line | (초청발표1)Nuclear Safety and R&D (Part-I) | WonPil Baek(KAERI) | - | - |
2020-Autumn | 5B : 원자력열수력 (Nuclear Thermal Hydraulics) | 12.17(Thu) 14:00 | On-line | (초청발표2)Nuclear Safety and R&D (Part-II) | WonPil Baek(KAERI) | - | - |
2020-Autumn | 5B : 원자력열수력 (Nuclear Thermal Hydraulics) | 12.17(Thu) 14:30 | On-line | Preliminary Safety Analysis Results of Lead Cooled Fast Reactor Design using MARS Code | Ji Yong Kim, Tung Dong Cao Nguyen, Deokjung Lee, and In Cheol Bang(UNIST) | PDF보기 | - |
2020-Autumn | 5B : 원자력열수력 (Nuclear Thermal Hydraulics) | 12.17(Thu) 14:50 | On-line | APR1400 MFLB Safety Analysis using MARS-KS CTF Sub-Channel Analysis Module and Parallelization Challenges | Nhan Hien Hoang, Younshil Kim, Young-Kyun Kwack, Sung-Hwan Bae, and Suk-Ku Sim(EN2T) | PDF보기 | PPT보기 |
2020-Autumn | 5B : 원자력열수력 (Nuclear Thermal Hydraulics) | 12.17(Thu) 15:10 | On-line | Coupling Between Subchannel Analysis Module of CUPID and Fuel Rod Analysis Code FINIX for Transient Simulation: Preliminary Analysis | Jang Keun Park and Hyoung Kyu Cho(SNU) | PDF보기 | - |
2020-Autumn | 5B : 원자력열수력 (Nuclear Thermal Hydraulics) | 12.17(Thu) 15:30 | On-line | MARS-KS Simulation of a Vertical Heat Pipe with Finned Air-cooled Condenser | Sangmin Park, Jonghwi Choi, and Hyungdae Kim(KHU) | PDF보기 | - |
2020-Autumn | 5B : 원자력열수력 (Nuclear Thermal Hydraulics) | 12.17(Thu) 15:50 | On-line | Multi-Physics Simulation for Load Follow Operation | Abd El Rahman Abou El Ala, and Aya Diab(KINGS) | PDF보기 | PPT보기 |
2020-Autumn | 5B : 원자력열수력 (Nuclear Thermal Hydraulics) | 12.17(Thu) 16:10 | On-line | BEPU Evaluation for APR1400 MSLB Accident using Artificial Intelligence | Salama Alketbi, Abd El Rahman Abou El Ala, Osama ALatawneh, Muhammad Wazif Bin Mohd Sallehhudin, and Aya Diab(KINGS) | PDF보기 | PPT보기 |
2020-Autumn | 5C : 원자력열수력 (Nuclear Thermal Hydraulics) | 12.18(Fri) 09:00 | On-line | (초청발표)Experimental study in KAERI for Containment Thermal Hydraulics of Advanced PWR | Byoung-Uhn BAE(KAERI) | - | - |
2020-Autumn | 5C : 원자력열수력 (Nuclear Thermal Hydraulics) | 12.18(Fri) 09:40 | On-line | A Preliminary Study of Subcooled Flow Boiling Critical Heat Flux on Cr-Coated Zr-Based Tube for Accident- Tolerant Fuel Cladding Application | Namgook Kim, Hong Hyun Son, and Sung Joong Kim(HYU) | PDF보기 | - |
2020-Autumn | 5C : 원자력열수력 (Nuclear Thermal Hydraulics) | 12.18(Fri) 10:00 | On-line | CFD Analysis of Heat Removal Capability in a Natural Circulation Loop with Phase Change Material | Hyunseop So, Insik Ra, Giyoung Tak, and Haeyong Jeong(Sejong Univ.) | PDF보기 | PPT보기 |
2020-Autumn | 5C : 원자력열수력 (Nuclear Thermal Hydraulics) | 12.18(Fri) 10:20 | On-line | Flow Structure Visualization Inside Subchannels of 6x12 Rod Bundle: A Preliminary Report | Hyeokjun Byeon, Seok Kim, Hae-Seob Choi, Byong Guk Jeon, Young-Jung Youn, and Sang-Ki Moon(KAERI) | PDF보기 | - |
2020-Autumn | 5C : 원자력열수력 (Nuclear Thermal Hydraulics) | 12.18(Fri) 10:40 | On-line | The Dropwise Condensation Heat Transfer Characteristics of CNT/OTS Layered Surface Associated with Non-Condensable Gas Effect | Taeseok Kim and Sung Joong Kim(HYU), Jaemin Lee, and Wonjoon Choi(KU) | PDF보기 | PPT보기 |
2020-Autumn | 5C : 원자력열수력 (Nuclear Thermal Hydraulics) | 12.18(Fri) 11:00 | On-line | Deep Learning and Acoustic Signal-based Pool Boiling Monitoring System | Do Yeong Lim and In Cheol Bang(UNIST) | PDF보기 | - |
Last Modified : 1998-Autumn