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학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2023-Spring 1A : 원자로시스템기술 (Reactor System Technology) 5.18(Thu) 11:20 201A (2F) Numerical Investigation of Heat Transfer Characteristics in Wire-Wrapped 19-pin Fuel Assembly Yohan Jung, Jongtae Kim, and Jonggan Hong(KAERI) PDF보기 -
2023-Spring 1A : 원자로시스템기술 (Reactor System Technology) 5.18(Thu) 11:40 201A (2F) Benchmark Tests of GAMMA+ Using EBR-II BOP Experiments Hyeonil Kim, Nam-il Tak, and Jonggan Hong(KAERI) PDF보기 -
2023-Spring 1A : 원자로시스템기술 (Reactor System Technology) 5.18(Thu) 12:00 201A (2F) Feasibility Evaluation of the Passive Molten Salt Fast Reactor (PMFR) Concept: A Parametric Sensitivity Analysis of Helical Coil Heat Exchangers and Supercritical Carbon Dioxide Power Conversion Systems Jihun Im, Jea Hyung Park, Juhyeong Lee, Won Jun Choi, Yun Sik Cho, and Sung Joong Kim(HYU) PDF보기 -
2023-Spring 1B : 원자로시스템기술 (Reactor System Technology) 5.18(Thu) 13:30 201A (2F) Gap Material and Raidial Geometry Modeling Dependency on a T/H Analysis in a Channel of CANDU6 Reactor Eun Hyun Ryu and Jong Yub Jung(KAERI) PDF보기 PPT보기
2023-Spring 1B : 원자로시스템기술 (Reactor System Technology) 5.18(Thu) 13:50 201A (2F) Preliminary Safety Analysis of CANDU Irradiated Fuel-Bay Using MARS-KS code: Part (I). Hypothetical Loss-of-Coolant-Accident Jun-young Kang, Dong Gun Son, Yong Mann Song, Jong Yeob Jung, and Jun Ho Bae(KAERI) PDF보기 -
2023-Spring 1B : 원자로시스템기술 (Reactor System Technology) 5.18(Thu) 14:10 201A (2F) Preliminary Safety Analysis of CANDU Irradiated Fuel-Bay Using MARS-KS code: Part (II). Hypothetical Loss-of-Cooling Accident Jun-young Kang, Dong Gun Son, Yong Mann Song, Jong Yeob Jung, and Jun Ho Bae(KAERI) PDF보기 -
2023-Spring 1B : 원자로시스템기술 (Reactor System Technology) 5.18(Thu) 14:50 201A (2F) Residual Stress and Intergranular(IG) Crack of Feeder Pipe in CANDU Reactor SungSoo Kim and Jong Yeop Jung(KAERI) PDF보기 -
2023-Spring 1B : 원자로시스템기술 (Reactor System Technology) 5.18(Thu) 15:10 201A (2F) Consideration of Water Leak through Concrete Wall Cracks in CANDU Spent Fuel Pool Jong Yeob Jung, Jun-young Kang, and Jun Ho Bae(KAERI), Sunil Nizahwan(Prolet Inc.) PDF보기 -
2023-Spring 1C : 원자로시스템기술 (Reactor System Technology) 5.19(Fri) 09:00 201A (2F) Passive Frequency Control Characteristics of S-CO2 Direct-Cycle Micro Modular Reactor Seongmin Son(KNU), Jeong Yeol Baek(KAIST) PDF보기 -
2023-Spring 1C : 원자로시스템기술 (Reactor System Technology) 5.19(Fri) 09:20 201A (2F) Verification and Validation of Aerosol Analysis Module in the MENTAS Code Nam-il Tak, Sung Nam Lee, and Tae Young Han(KAERI) PDF보기 -
2023-Spring 1C : 원자로시스템기술 (Reactor System Technology) 5.19(Fri) 09:40 201A (2F) Application of Open-air Brayton Cycle to sCO2-cooled KAIST Micro Modular Reactor Yeongchan Kim, Sungwook Choi, and Jeong Ik Lee(KAIST) PDF보기 -
2023-Spring 1C : 원자로시스템기술 (Reactor System Technology) 5.19(Fri) 10:00 201A (2F) Peak Overpressure Predictions for a SRI Test by Correlation Methods and a CFD Analysis Hyung Seok Kang and Keun Sang Choi(KAERI), Sang Dough Park(SNU) PDF보기 -
2023-Spring 1C : 원자로시스템기술 (Reactor System Technology) 5.19(Fri) 10:20 201A (2F) Load Following Capability of KAIST-MMR for Marine Application Jeong Yeol Baek and Jeong Ik Lee(KAIST) PDF보기 -
2023-Spring 1C : 원자로시스템기술 (Reactor System Technology) 5.19(Fri) 11:00 201A (2F) Experimental Study on the High-Temperature Steam Supply System Using Helium Loop for Reliable Sin-Yeob Kim, Sung-Deok Hong, Kyung-Jun Kang, and Chan-Soo Kim(KAERI) PDF보기 -
2023-Spring 1C : 원자로시스템기술 (Reactor System Technology) 5.19(Fri) 11:20 201A (2F) A Bendable Liquid Metal Heat Pipe: Numerical Assessment and Experimental Validation Byung Ha Park, Ho Sik Kim, and Chan Soo Kim(KAERI) PDF보기 -
Last Modified : 1998-Autumn