학술발표회 논문집
| Year | Div | Date/Time | ROOM | Title | Author | Abstract File | Presentation File |
|---|---|---|---|---|---|---|---|
| 2025-Spring | 4H : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.22(Thu) 13:00 | Lobby | Nuclear and Thermal Sensitivity Analysis of a Double-Layer Thermal Medium Capsule in Neutron Irradiation Tests | Jong Woo Kim, Hae Sun Jeong, Junesic Park, Ye Eun Na, Ki Nam Choo, and Seong Woo Yang(KAERI) | PDF보기 | - |
| 2025-Spring | 4H : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.22(Thu) 13:00 | Lobby | Design Thickness Variation in i-SMR Reactor Vessels: A Comparison of ASME BPVC Sec. III Subsections NB and NE | Beom-jin Kim and Jin-Ha Hwang(Pukyong National Univ.) | PDF보기 | - |
| 2025-Spring | 4H : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.22(Thu) 13:00 | Lobby | Methodologies for Acoustic Induced Vibration Analysis of Reactor Vessel Internals at Fluid-Structure Interfaces | Chiwoong Ra, Hyungyu Roh, and No-cheol Park(Yonsei Univ.) | PDF보기 | - |
| 2025-Spring | 5A : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.22(Thu) 09:00 | 301 | Experimental Investigation of Air-water Two-phase Flow through Inclined Circular Channel with Wire-mesh Sensor: Preliminary Test | Hyukjae Ko, Taehwi Kim, Goon-Cherl Park, and Hyoung Kyu Cho(SNU) | PDF보기 | - |
| 2025-Spring | 5A : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.22(Thu) 09:20 | 301 | Reduction of Radiative Heat Loss in Small Modular Reactors Through Thermal Radiation Shielding: An Experimental and CFD Approach | Beomjin Jeong, Geunyoung Byeon, Namgook Kim, and Sung Joong Kim(HYU) | PDF보기 | - |
| 2025-Spring | 5A : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.22(Thu) 09:40 | 301 | Local Thermal Analysis using an Optical Fiber Eemperature Sensor in a Flow Boiling Heat Transfer | Donghwi Lee, Hyeon Taek Nam, and Seungro Lee(Jeonbuk National Univ.) | PDF보기 | - |
| 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 | - |
Last Modified : 1998-Autumn
