학술발표회 논문집
Year | Div | Date/Time | ROOM | Title | Author | Abstract File | Presentation File |
---|---|---|---|---|---|---|---|
2024-Spring | 0C : 개회식 및 주요행사 (Opening and Events) | 5.9(Thu) 18:00 | 한라홀 (3F) | 만찬 및 학생경진대회 | PDF보기 | - | |
2024-Spring | 0C : 개회식 및 주요행사 (Opening and Events) | 5.9(Thu) 12:00 | 오션뷰 (5F) | 제97차 평의원회 | - | - | |
2024-Spring | 1A : 원자로시스템기술 (Reactor System Technology) | 5.9(Thu) 09:00 | 301 (1F) | An Effect of Axial Conduction On Liquid Air Storage Tank for Liquid Air Energy Storage System Coupled to Nuclear Power Plant | Jung Hwan Park and Jeong Ik Lee(KAIST) | PDF보기 | - |
2024-Spring | 1A : 원자로시스템기술 (Reactor System Technology) | 5.9(Thu) 09:20 | 301 (1F) | A Study on Secondary Frequency Operation in APR1400 Using Mode-K+ | Husam Khalefih, Yunseok Jeong, and Yonghee Kim(KAIST) | PDF보기 | - |
2024-Spring | 1A : 원자로시스템기술 (Reactor System Technology) | 5.9(Thu) 09:40 | 301 (1F) | Preliminary Validation of GAMMA+ code for Packed Bed Thermal Storage System | Nayoung Kim, Jung Hwan Park, and Jeong Ik Lee(KAIST) | PDF보기 | - |
2024-Spring | 1A : 원자로시스템기술 (Reactor System Technology) | 5.9(Thu) 10:00 | 301 (1F) | An Application of Design for 3D printing to APR1400 Nuclear Fuel Spacer Grid | Seungmin Kim and Ihn Namgung(KINGS) | PDF보기 | - |
2024-Spring | 1A : 원자로시스템기술 (Reactor System Technology) | 5.9(Thu) 10:20 | 301 (1F) | An Evaluation of Normal Contact of CSB Oppening and RV Outlet Nozzle | Christopher Omondi and Ihn Namgung(KINGS) | PDF보기 | - |
2024-Spring | 1A : 원자로시스템기술 (Reactor System Technology) | 5.9(Thu) 11:00 | 301 (1F) | Modal Analysis of CSB and RV Assembly in Case of CSB Slanted Contact with RV Outlet Nozzle | Quang Hieu Pham and Ihn Namgung(KINGS) | PDF보기 | - |
2024-Spring | 1A : 원자로시스템기술 (Reactor System Technology) | 5.9(Thu) 11:20 | 301 (1F) | Improvement of PWR Fuel Spacer Grid Model Based on Experimental Results | Minhee Kim and Ihn Namgung(KINGS) | PDF보기 | - |
2024-Spring | 1A : 원자로시스템기술 (Reactor System Technology) | 5.9(Thu) 11:40 | 301 (1F) | Modal Analysis of CSB and RV Assembly for Normal Contact | Niniek Yasintha and Ihn Namgung(KINGS) | PDF보기 | - |
2024-Spring | 1A : 원자로시스템기술 (Reactor System Technology) | 5.9(Thu) 12:00 | 301 (1F) | Sensitivity Analysis for Metal Containment Vessel Wall Thickness to Accommodate Flooding Safety System using MELCOR Code | Hyo Jun An, Jae Hyung Park, Jinho Song, and Sung Joong Kim(HYU) | PDF보기 | - |
2024-Spring | 1B : 원자로시스템기술 (Reactor System Technology) | 5.9(Thu) 13:30 | 301 (1F) | Preliminary Thermal Analysis of the K-MSR | Joonho Jeong, Gyeong-Hoi Koo, and Taewoo Kim(KAERI) | PDF보기 | - |
2024-Spring | 1B : 원자로시스템기술 (Reactor System Technology) | 5.9(Thu) 13:50 | 301 (1F) | Off-Gas System for KMSR | Yonghee Ryu, Jinsung Kwak, Jinho Oh, and Gyeong-Hoi Koo(KAERI) | PDF보기 | - |
2024-Spring | 1B : 원자로시스템기술 (Reactor System Technology) | 5.9(Thu) 14:10 | 301 (1F) | Hydraulic Resistance Modelling of the Porous Media Approaches for a Pool-type Sodium-cooled Fast Reactor | Churl Yoon, Huee-Youl Ye, and Jae Hyuk Eoh(KAERI) | PDF보기 | PPT보기 |
2024-Spring | 1B : 원자로시스템기술 (Reactor System Technology) | 5.9(Thu) 14:50 | 301 (1F) | CFD Analysis and Benchmarking of XX09 Subassembly for EBR-II Shutdown Heat Removal Tests SHRT-45 | Junbeom Park and Jae-Ho Jeong(Gachon Univ.) | PDF보기 | - |
Last Modified : 1998-Autumn