학술발표회 논문집
| Year | Div | Date/Time | ROOM | Title | Author | Abstract File | Presentation File |
|---|---|---|---|---|---|---|---|
| 2024-Spring | 5C : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.10(Fri) 09:20 | 202B (2F) | CFD Investigation of a MONJU 169-Pin Wire-Wrapped Fuel Assembly Experiment | Seongchul Park and Jae-Ho Jeong(Gachon Univ.) | PDF보기 | - |
| 2024-Spring | 5C : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.10(Fri) 09:40 | 202B (2F) | Effect of Asymmetric Inlet Mass Flow Conditions on Flow Behavior Inside Subchannel of a 6×12 Rod Bundle | Jun Yeong Jung, Seok Kim, and Hae-Seob Choi(KAERI) | PDF보기 | - |
| 2024-Spring | 5C : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.10(Fri) 10:00 | 202B (2F) | Evaluation of Condensation Models for the Outer Wall under Pure Steam Condition | Dongwon Jeong and Byongjo Yun(Pusan National Univ.), Jinhoon Kang(KIMM), SangGyun Nam(FNC Tech.) | PDF보기 | - |
| 2024-Spring | 5C : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.10(Fri) 10:20 | 202B (2F) | Experimental Investigation on Wall Friction Factor in a Vertical Annulus Channel under Natural Circulation \'Water Flow Conditions | Seongbae Park, Youngchang Ko, and Byongjo Yun(Pusan National Univ.) | PDF보기 | - |
| 2024-Spring | 5C : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.10(Fri) 11:00 | 202B (2F) | Investigation of Thermal Hydraulic Characteristics of PCCS According to the Containment Size | Sang Gyun Nam, Youngjae Park, Jehee Lee, Jungjin Bang, and SeongSu Jeon(FNC Tech.) | PDF보기 | - |
| 2024-Spring | 5C : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.10(Fri) 11:20 | 202B (2F) | Modeling Steam Condensation on Passive Heat Sinks within Containment for Realistic Analysis of Heat Removal Behavior | Jia Yu and Yeon-Gun Lee(Sejong Univ.) | PDF보기 | - |
| 2024-Spring | 5C : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.10(Fri) 11:40 | 202B (2F) | Preliminary CFD Analysis of Spreading and Solidification of FLiNaK and KCl-UCl3 | Ye Hwan Chun, Jin Ho Song, Yun Sik Cho, Juhyeong Lee, Won Jun Choi, Jihun Im, and Sung Joong Kim(HYU), Sang Mo An and Sung-Il Kim(KAERI) | PDF보기 | - |
| 2024-Spring | 5C : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.10(Fri) 12:00 | 202B (2F) | Validation of RV Model in CUPID Code Against a Rod Bundle Test, SIRIUS-3D, and Design of a New Rod Bundle Test | Byong Guk Jeon, Jae Ryong Lee, Sang-Ki Moon, HaeSeop Choi, and Seok Kim(KAERI), Hyungmin Park(SNU) | PDF보기 | - |
| 2024-Spring | 5D : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.10(Fri) 09:00 | 203 (2F) | Calibration of Fuel Assembly Mockup of Advanced Research Reactor | Taeil Kim, Yohan Lee, Donkoan Hwang, WooHyun Jung, Nakjun Choi, and HangJin Jo(POSTECH), Jonghark Park, Hyung Min Son, Huiyung Kim, Kiwon Song(KAERI) | PDF보기 | - |
| 2024-Spring | 5D : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.10(Fri) 09:20 | 203 (2F) | Numerical Simulation for ROCOM PTS Test using Generalized k-ω Turbulence Model | Dong-Hyeon Choi and Yoon-Suk Chang(KHU) | PDF보기 | - |
| 2024-Spring | 5D : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.10(Fri) 09:40 | 203 (2F) | Parametric Study of the Fuel Salt Drain System Design of K-MSR | Dongyeol Yeo, Chan Lee, and Gyeong-Hoi Koo(KAERI) | PDF보기 | - |
| 2024-Spring | 5D : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.10(Fri) 10:00 | 203 (2F) | Review of Prediction Capability of System Analysis Code for Density Wave Oscillation | Dong-Young Lee, Seong-Su Jeon, Jan Hruskovic, YoungJae Park, and Jungjin Bang(FNC Tech.) | PDF보기 | - |
| 2024-Spring | 5D : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.10(Fri) 10:20 | 203 (2F) | Rolling Motion Effect on Differential Pressure Measurement in NEOUL-R Flow Boiling Experiment | Hyukjae Ko, Jin-Seong Yoo, Heepyo Hong, Ja Hyun Ku, Giwon Bae, Goon-Cherl Park, and Hyong Kyu Cho(SNU) | PDF보기 | - |
| 2024-Spring | 5D : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.10(Fri) 11:00 | 203 (2F) | Sensitivity Assessment of Gas Injection Effect in Terms of Natural Circulation Performance through Adiabatic Two-Phase Experiment | Won Jun Choi, Jae Hyung Park, Seung Gyu Hyeon, and Sung Joong Kim(HYU) | PDF보기 | - |
| 2024-Spring | 5D : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.10(Fri) 11:20 | 203 (2F) | Temperature Prediction of Cladding in CANDU Spent Fuel Dry Storage Canister using CFD Code and Uncertainty Analysis | Tae Gang Lee and Jae Jun Jeong(Pusan National Univ.), Tae Hyung Na(KHNP CRI) | PDF보기 | - |
Last Modified : 1998-Autumn
