학술발표회 논문집 (ISSN: 3140-1864)
| Year | Div | Date/Time | ROOM | Title | Author | Abstract File | Presentation File |
|---|---|---|---|---|---|---|---|
| 2025-Spring | 5A : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.22(Thu) 10:00 | 301 | Experimental Investigation of Radiative and Convective Heat Transfer Coefficients in a Metal Containment Vessel for Small Modular Reactors under Steady-State Conditions | Geunyoung Byeon, Beomjin Jeong, Namgook Kim, JinHo Song, JoonEon Yang, and Sung Joong Kim(HYU) | PDF보기 | - |
| 2025-Spring | 5A : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.22(Thu) 10:20 | 301 | Preliminary Experiment on Individual Hydrogen Bubble Behaviors in Alkaline Water Electrolysis | Seheun Kwon, Seungju Lee, Shinil Kim, and Haekyun Park(Kyungpook National Univ.) | PDF보기 | - |
| 2025-Spring | 5A : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.22(Thu) 11:00 | 301 | Experimental Investigation on Augmentation of Critical Current Density in Alkaline Water Electrolysis using Shroud Structure | Jaeduck Seo, Jeonghun Seo, and Haekyun Park(Kyungpook National Univ.) | PDF보기 | - |
| 2025-Spring | 5A : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.22(Thu) 11:20 | 301 | Measurements of Bubbly Flow on a 4x4 Rod Bundle Under Oscillating Conditions | Tan Hung Hoang, Myung Ho Kim, and Byoung Jea Kim(Chungnam National Univ.) | PDF보기 | - |
| 2025-Spring | 5A : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.22(Thu) 11:40 | 301 | Experimental Observation of Bubble Behavior and CHF on a Downward-Facing Surface in Pool Boiling | Young Hee Kim, Young Hoon Jeong, and Dong Hun Shin(KAIST), Min Suk Lee(Texas A M Univ.), Dong Hoon Kam(Argonne National Laboratory) | PDF보기 | - |
| 2025-Spring | 5B : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.22(Thu) 09:00 | 302 | Analytical and Numerical Evaluation of Wall Thermal Boundary Conditions in Free Convective Thin Plates with Internal Heat Generation | Moon Won Song(Jeonbuk National Univ.) | PDF보기 | - |
| 2025-Spring | 5B : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.22(Thu) 09:20 | 302 | Development of Virtual Nuclear Reactor for Design and Demonstration of SMRs | Yun Je Cho, Sung Hoon Choi, and Seong Ju Do(KAERI) | PDF보기 | - |
| 2025-Spring | 5B : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.22(Thu) 09:40 | 302 | Numerical Analysis of Core Melt Solidification and Spreading Behavior Using the MPS Method | Cho Yun-Sik, Kim Sung Joong, and Song JinHo(HYU) | PDF보기 | - |
| 2025-Spring | 5B : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.22(Thu) 10:00 | 302 | Conceptual Problem-Based Verification of the Containment Thermal-Hydraulics Analysis Module for Severe Accident Analysis | Kum Ho Han, Jehee Lee, and Yeon-Jun Choo(FNC Tech.) | PDF보기 | - |
| 2025-Spring | 5B : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.22(Thu) 10:20 | 302 | Reactor Power and Thermal Safety Margin in a Natural Circulation Small Modular Reactor Adopting TOP Lattice Core Design | Jae Hyung Park, Yujin Kim, Hyo Jun An, Jihun Im, JinHo Song, and Sung Joong Kim(HYU) | PDF보기 | - |
| 2025-Spring | 5B : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.22(Thu) 11:00 | 302 | CFD of Two-Phase Natural Circulation in the Presence of Non-Condensable Gas | Nam Kyu Ryu and Byeong Jae Kim(Chungnam National Univ.) | PDF보기 | PPT보기 |
| 2025-Spring | 5B : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.22(Thu) 11:20 | 302 | A Study on the Thermal–hydraulic Characteristics of Zigzag Channel PCHE using PIV Experiment and CFD | Yoomyeong Lee, YeonGyu Lee, and Donghwi Lee(Jeonbuk National Univ.), Seongmin Lee, HongBeom Park, and Kyoungwoo Seo(KAERI) | PDF보기 | - |
| 2025-Spring | 5B : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.22(Thu) 11:40 | 302 | Evaluation of Effects for Subchannel-scale Rod Deformation during LBLOCA | Yunseok Lee and Taewan Kim(Incheon National Univ.) | PDF보기 | - |
| 2025-Spring | 5C : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.22(Thu) 13:30 | 301 | Experiments on Charging of Cold Thermal Energy by Mass Flow Rate of Packed Bed Cryogenic Energy Storage System | Dahui Kwack, Chunsik Lee, and Choongsub Yoem(IAE) | PDF보기 | - |
| 2025-Spring | 5C : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.22(Thu) 13:50 | 301 | Exploring the Feasibility of 3D-printed High-temperature Heat Pipe for Nuclear Reactor Application: Seal Testing and Water Charged Thermal Cycling Evaluation | Almanzo Arjuna, Faruk Celik, Dong hun Lee, and In cheol Bang(UNIST) | PDF보기 | - |
Last Modified : 1998-Autumn
