학술발표회 논문집
| Year | Div | Date/Time | ROOM | Title | Author | Abstract File | Presentation File |
|---|---|---|---|---|---|---|---|
| 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 | - |
| 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 | - |
| 2025-Spring | 5C : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.22(Thu) 14:10 | 301 | Sensitivity Analysis for PAFS Cooling during an SBLOCA under PECCS Operation using ATLAS Test Facility | Jin-Hwa Yang, Byoung-Uhn Bae, Seok Cho, Yu-Sun Park, Nam-Hyun Choi, Jae-Bong Lee, Jong-Rok Kim, Jun-Yeong Jung, and Kyoung-Ho Kang(KAERI) | PDF보기 | - |
| 2025-Spring | 5C : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.22(Thu) 14:50 | 301 | Design and Development of Experimental Facility for Supercritical Two-Stage High-Pressure Ratio Centrifugal Compressor | Gibbeum Lee, Jae Eun Cha, and Han SEO(KAERI), SI Woo Lee(Jinsol Turbo) | PDF보기 | - |
| 2025-Spring | 5C : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.22(Thu) 15:10 | 301 | Experimental Investigation on Convective Heat Transfer in a Vertical Annulus under Natural Circulation Water Flow Conditions | Seongbae Park, Youngchang Ko, and Byongjo Yun(PNU) | PDF보기 | - |
| 2025-Spring | 5C : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.22(Thu) 15:30 | 301 | Thermal-Hydraulic Behavior of LOCA during Shutdown Operation: C4.2 Test Findings from OECD/NEA ATLAS Phase 3 Project | Jae Bong Lee, Byoung-Uhn Bae, Yusun Park, Jongrok Kim, Seok Cho, and Kyoung-Ho Kang(KAERI) | PDF보기 | - |
| 2025-Spring | 5D : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.22(Thu) 13:30 | 302 | Numerical Evaluation of Thermal Behavior of Freeze Valve System for K-MSR | Sungbo Lee, Chan Lee, and Gyeong-Hoi Koo(KAERI), Hyoungsuk Yu(KAIST) | PDF보기 | - |
| 2025-Spring | 5D : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.22(Thu) 13:50 | 302 | Improvements of First and Total Dry-out Models for the Helical Coiled SGs | Yujeong Ko and Hyoung Kyu Cho(SNU) | PDF보기 | - |
| 2025-Spring | 5D : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.22(Thu) 14:10 | 302 | Pressure Loss Prediction during Sudden Expansion using Artificial Neural Network | Jong Hui Lee, Cheong Bong Chang, Youngmin Bae, and Seongyeob Ryu(KAERI), Gyeongseop Lee(SNU), Seong Bae Pak(TAESUNG Software and Engineering Inc.), Jin Ho Oh(Kyungpook National Univ.) | PDF보기 | - |
| 2025-Spring | 5D : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.22(Thu) 14:50 | 302 | Development of a FLUENT-Based Thermal-Hydraulic Analysis Code Framework for Steam Generators using pyAnsys | Bumjin Cho, Jinsu Kim, and Minseop Song(HYU), Giwon Bae and Hyoungkyu Cho(SNU) | PDF보기 | - |
Last Modified : 1998-Autumn
