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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