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학술발표회 논문집 (ISSN: 3140-1864)

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2026-Autumn 5D : 원자력 열수력 (Nuclear Thermal Hydraulics) 10.30(Fri) 11:20 300A Evaluation of Thermal Conductivity of TRISO Fuel using CFD Code Jeonghyun Kim, Seongho Lee, Chunghyun Park, Doyeong Lee, Giyoung Tak, In-sik Ra, and Hae-yong Jeong(Sejong Univ.) PDF보기 -
2026-Autumn 5D : 원자력 열수력 (Nuclear Thermal Hydraulics) 10.30(Fri) 11:40 300A Numerical Investigation on Hydrodynamic Load Redistribution and Localized Clogging Characteristics of Seawater Intake Drum Screens SeongMin Park(KHNP), TaeGang Lee and JaeJun Jung(PNU) PDF보기 -
2026-Autumn 5D : 원자력 열수력 (Nuclear Thermal Hydraulics) 10.30(Fri) 12:00 300A Toward Real-Time GPU-Accelerated Lattice Boltzmann LES for Molten Salt Reactor Thermal Hydraulics: Benchmark Validation and Demonstration Suhyeon Kim, Jiho Kim, and Eung Soo Kim(SNU) PDF보기 -
2026-Autumn 5E : 원자력 열수력 (Nuclear Thermal Hydraulics) 10.29(Thu) 13:30 202 Preliminary Modification of the SPACE Code Condensation Model for Superheated Steam Condensation in the i-SMR Containment Vessel Chang Won Lee and Jong-Hyuk Lee(KAERI) PDF보기 -
2026-Autumn 5E : 원자력 열수력 (Nuclear Thermal Hydraulics) 10.29(Thu) 13:50 202 Application and Validation of External Condensation Models for Horizontal Tubes in MARS-KS Taeyeon Min, Yeongjae Cho, and Jeong Ik Lee(KAIST) PDF보기 -
2026-Autumn 5E : 원자력 열수력 (Nuclear Thermal Hydraulics) 10.29(Thu) 14:10 202 CFD Analysis of Two-Phase Flow Instability in a Passive Containment Cooling System Yong Kab Lee(SIMEX), Jong Chull Jo(TIUM solutions) PDF보기 -
2026-Autumn 5E : 원자력 열수력 (Nuclear Thermal Hydraulics) 10.29(Thu) 14:50 202 Preliminary Study on a Simplified Two-Phase-Flow Model for the Dynamic Response of Passive Emergency Core Cooling System Valves Jeong-won Han, Young Seok Bang, and Youngjae Park(FNC Tech.) PDF보기 -
2026-Autumn 5E : 원자력 열수력 (Nuclear Thermal Hydraulics) 10.29(Thu) 15:10 202 A Scheme to Predict Discharge Coefficient of Long Multi-hole Orifices Perforated in PECCS Valves Young Seok Bang, JeongWon Han, Youngjae Park, Seong-Su Jeon, and Soon-Joon Hong(FNC Tech.) PDF보기 -
2026-Autumn 5E : 원자력 열수력 (Nuclear Thermal Hydraulics) 10.29(Thu) 15:30 202 Uncertainty Quantification on Critical Flow for an IBLOCA Application Hyun-Sik Park, Chiwoong Choi, and Seung-Wook Lee(KAERI) PDF보기 -
2026-Autumn 5F : 원자력 열수력 (Nuclear Thermal Hydraulics) 10.30(Fri) 09:00 300B Assessment of Existing CHF Correlations for the Operating Conditions and Design Region of the i-SMR Seojun Park and Kyung Mo Kim(KENTECH) PDF보기 -
2026-Autumn 5F : 원자력 열수력 (Nuclear Thermal Hydraulics) 10.30(Fri) 09:20 300B Improvement of CHF Prediction under Non-Uniform Axial Power Profiles through AI-Based Memory-Effect Correction Hyunjun Jang and Kyung Mo Kim(KENTECH) PDF보기 -
2026-Autumn 5F : 원자력 열수력 (Nuclear Thermal Hydraulics) 10.30(Fri) 09:40 300B Improvement of Drift-flux Correlations in MARS-KS for Inclined two-phase Flow: Model Implementation and Validation against Air-water Tests Eunji Lee and Hyoung Kyu Cho(SNU) PDF보기 -
2026-Autumn 5F : 원자력 열수력 (Nuclear Thermal Hydraulics) 10.30(Fri) 10:00 300B Assessment of Pressure Drop Predictability of MARS-KS in Helically Coiled Tubes Yunseok Lee and Taewan Kim(Incheon National Univ.) PDF보기 -
2026-Autumn 5F : 원자력 열수력 (Nuclear Thermal Hydraulics) 10.30(Fri) 10:20 300B Preliminary Study of a Thermal-Hydraulic Model for Helically Coiled Once-Through Steam Generator Design Analysis Nhan Hien Hoang, Jinwook Choi, Sera Jeon, and Seong-Su Jeon(FNC Tech.) PDF보기 -
2026-Autumn 5F : 원자력 열수력 (Nuclear Thermal Hydraulics) 10.30(Fri) 11:00 300B Thermal-Hydraulic Closure and Maintainability of a Natural-Circulation OTSG with an Integral Pressurizer and Removable ECT Cartridge for a 140 MWe SMR SE YUP LEE(KONEC) PDF보기 -
Last Modified : 1998-Autumn