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학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2025-Spring 1B : 원자로시스템기술 (Reactor System Technology) 5.23(Fri) 09:40 삼다홀B Preliminary Tritium Transport Analysis in the 90MWth HTGR System SUNG NAM LEE, Nam-il Tak, Sung Hoon Choi, and Chan Soo Kim(KAERI) PDF보기 -
2025-Spring 1B : 원자로시스템기술 (Reactor System Technology) 5.23(Fri) 10:00 삼다홀B OECD/NEA HTGR Lower Plenum Benchmark Study Result from KAIST Moon Hyeok Kang and Jeong Ik Lee(KAIST) PDF보기 -
2025-Spring 1B : 원자로시스템기술 (Reactor System Technology) 5.23(Fri) 10:20 삼다홀B Validation of Solid Oxide Cell and Stack Model Using SIMULINK for Gas-Cooled Reactor Analysis Jiwon Ahn and Hyoung Kyu Cho(SNU), Byung Ha Park(KAERI) PDF보기 -
2025-Spring 1C : 원자로시스템기술 (Reactor System Technology) 5.22(Thu) 13:00 Lobby Thermodynamic Analysis of Liquid Air Energy Storage System Integrated to Pressurized Water Reactor with Consideration of Composition Change of Liquefied Air after Various Cryogenic Expansion Processes Yong Jae Chae and Jeong Ik Lee(KAIST) PDF보기 -
2025-Spring 1C : 원자로시스템기술 (Reactor System Technology) 5.22(Thu) 13:00 Lobby Investigation of the Dynamic Characteristic Similarity of the Experimental Reactor for Comprehensive Vibration Assessment Program (CVAP) Choengryul Choi, Won Man Park, Dae Kyung Choi, and Seung Mok Yoo(Elsoltec), Tae Soon Kwon and Woo Shik Kim(KAERI), Do Young Ko and Kyu Hyung Kim(KHNP) PDF보기 -
2025-Spring 1C : 원자로시스템기술 (Reactor System Technology) 5.22(Thu) 13:00 Lobby Case study for Increment of Ultimate Heat Sink Temperature due to Increase of seawater Temperature Joohyung Jung and Seongmin Son(Kyungpook National Univ.) PDF보기 -
2025-Spring 1C : 원자로시스템기술 (Reactor System Technology) 5.22(Thu) 13:00 Lobby Applicability of Existing Pressurizer Pressure Control Logics for Load-Following Operation of PWR-type SMR Using MTC-based Secondary Reactivity Control Semin Joo and Jeong Ik Lee(KAIST) PDF보기 -
2025-Spring 1C : 원자로시스템기술 (Reactor System Technology) 5.22(Thu) 13:00 Lobby Feasibility Analysis of Introducing Innovative SMR (i-SMR) in Developing Countries (Kazakhstan, Indonesia) Byungjoon Jung and Sin Jung Chang(KHNP CRI) PDF보기 -
2025-Spring 1C : 원자로시스템기술 (Reactor System Technology) 5.22(Thu) 13:00 Lobby Evaluation of the Flexible Operation Capability of an i-SMR Core Using RCS Outlet Temperature-Based Control Rod Operation Method Seongho Park, Nayeon Seo, Hwansoo Kim, and Junggyu Lee(KEPCO NF) PDF보기 -
2025-Spring 1C : 원자로시스템기술 (Reactor System Technology) 5.22(Thu) 13:00 Lobby Investigating Necessary Operating Conditions for TES Integrated to PWR SMRs to Maintain the Reactor Power Takhyun Chun, Gyudong Kim, Yong Jae Chae, and Jeong Ik Lee(KAIST) PDF보기 -
2025-Spring 1C : 원자로시스템기술 (Reactor System Technology) 5.22(Thu) 13:00 Lobby Preliminary Study on Interfacial Transfer Models on Water Surface to Predict Steam Pressurizer Behaviors Minkyu Lee and Seungyeob Ryu(KAERI) PDF보기 -
2025-Spring 1C : 원자로시스템기술 (Reactor System Technology) 5.22(Thu) 13:00 Lobby In-Containment Source Term Evaluation under SBO Induced Severe Core Damage Using MAAP-ISAAC in Wolsong Unit 2 Plants Y.M. Song, J.Y. Kang, J.H. Bae, and D.G. Son(KAERI) PDF보기 -
2025-Spring 1C : 원자로시스템기술 (Reactor System Technology) 5.22(Thu) 13:00 Lobby High-Temperature Fatigue Test on P91 Induction Bent Pipe of PGSFR for Applicability Analysis Tae-Won Na, Jong-Bum Kim, Chang-Gyu Park, and June Hyung Kim(KAERI) PDF보기 -
2025-Spring 1C : 원자로시스템기술 (Reactor System Technology) 5.22(Thu) 13:00 Lobby Creep Properties of P91 Induction Bent Pipe for PGSFR Tae-Won Na, Jong-Bum Kim, Chang-Gyu Park, and June Hyung Kim(KAERI) PDF보기 -
2025-Spring 1C : 원자로시스템기술 (Reactor System Technology) 5.22(Thu) 13:00 Lobby Creep Tests of P91 Elbow Pipe by Induction Bending Technology Jong-Bum Kim, Chang-Gyu Park, Tae-Won Na, and Junehyung Kim(KAERI) PDF보기 -
Last Modified : 1998-Autumn