학술발표회 논문집
| Year | Div | Date/Time | ROOM | Title | Author | Abstract File | Presentation File |
|---|---|---|---|---|---|---|---|
| 2023-Autumn | 5F : 원자력열수력 (Nuclear Thermal Hydraulics) | 10.26(Thu) 13:00 | Lobby (3F) | A Sensitivity Calculation of SMR Generated Superheated Steam using MARS | Sangjin Kim, Seulbin Park, Ungsoo Kim, and Seokjeong Park(KEPCO E&C) | PDF보기 | - |
| 2023-Autumn | 5F : 원자력열수력 (Nuclear Thermal Hydraulics) | 10.26(Thu) 13:00 | Lobby (3F) | Development of Pressure and Temperature Analysis Methodology for APR1400 Containment in CONTEMPT-LT/028 | Yongju Cho, Yoonsun Hong, Jaeyul Kim, Jaeseung Moon, and Sanggyu Lee(KEPCO E&C) | PDF보기 | - |
| 2023-Autumn | 5F : 원자력열수력 (Nuclear Thermal Hydraulics) | 10.26(Thu) 13:00 | Lobby (3F) | RCP Seal Leakage in the Loss of Ultimate Heat Sink Accident for APR1400 Nuclear Power Plant | Hyoung Kyoun Ahn, Min Seok Lee, and Seok Jung Park(KEPCO E&C) | PDF보기 | - |
| 2023-Autumn | 5F : 원자력열수력 (Nuclear Thermal Hydraulics) | 10.26(Thu) 13:00 | Lobby (3F) | Development of Multidimensional Flow Model of SPACE Code | Byoung Jae Kim(CNU), Jaeseok Heo and Seung Wook Lee(KAERI) | PDF보기 | - |
| 2023-Autumn | 5F : 원자력열수력 (Nuclear Thermal Hydraulics) | 10.26(Thu) 13:00 | Lobby (3F) | Analysis on Loss of Condenser Vacuum with a POSRV failure for APR1400 | YOU NYEONG SEOL, HYOUNG KYOUN AHN, MIN SEOK LEE, and SEOK JEONG PARK(KEPCO E&C) | PDF보기 | - |
| 2023-Autumn | 5F : 원자력열수력 (Nuclear Thermal Hydraulics) | 10.26(Thu) 13:00 | Lobby (3F) | CFD Analysis of the Cavitation Flow Features for the Centrifugal Pump with Different Numbers of Blade and Blade Angle | Gong-hee Lee(KINS), Yong Gap Lee(SIMEX) | PDF보기 | - |
| 2023-Autumn | 5F : 원자력열수력 (Nuclear Thermal Hydraulics) | 10.26(Thu) 13:00 | Lobby (3F) | Preliminary Assessment on Thermal Hydraulic Performance of Molten Salt and Metal Reactor (MSMR) by using FLUENT Code | Won Jun Choi, Juhyeong Lee, and Sung Joong Kim(HYU), Yonghee Kim(KAIST) | PDF보기 | - |
| 2023-Autumn | 5F : 원자력열수력 (Nuclear Thermal Hydraulics) | 10.26(Thu) 13:00 | Lobby (3F) | Analysis of Thermal Stratification and Turbulence Penetration of RCS Branch Piping | Sun-Joon Byun, Chong-Kuk Chun, Kang-Hoon Moon, and Hyung-Wook Jang(KEPCO NF) | PDF보기 | - |
| 2023-Autumn | 5F : 원자력열수력 (Nuclear Thermal Hydraulics) | 10.26(Thu) 13:00 | Lobby (3F) | Analysis of LOCV and MMPSMF on i-SMR for Setup of High Pressurizer Level Trip Setpoint | Ye Eun An, Se Young Ro, Sang Jin Lee, Min Shin Jung, and Seok Jeong Park(KEPCO E&C) | PDF보기 | - |
| 2023-Autumn | 5F : 원자력열수력 (Nuclear Thermal Hydraulics) | 10.26(Thu) 13:00 | Lobby (3F) | Validation of CAP Code for Containment Steam Injection Test in ATLAS-CUBE Facility | Byoung Uhn Bae, Jae Bong Lee, Yusun Park, Jongrok Kim, Seok Cho, and Kyoung Ho Kang(KAERI) | PDF보기 | - |
| 2023-Autumn | 5F : 원자력열수력 (Nuclear Thermal Hydraulics) | 10.26(Thu) 13:00 | Lobby (3F) | The Effect of Heat Flux Profile on Two-phase Flow Instability in Helical Tube Steam Generator | Seunghwan Oh, Doh Hyeon Kim, and Jeong Ik Lee(KAIST) | PDF보기 | - |
| 2023-Autumn | 5G : 원자력열수력 (Nuclear Thermal Hydraulics) | 10.26(Thu) 13:00 | Lobby (3F) | Thermodynamic Basic Validation for the Development of Containment Thermal-Hydraulic Analysis Module in Case of Severe Accident | Kum Ho Han, Bub-Dong Chung, and Yeon-Jun Choo(FNC Tech.) | PDF보기 | - |
| 2023-Autumn | 5G : 원자력열수력 (Nuclear Thermal Hydraulics) | 10.26(Thu) 13:00 | Lobby (3F) | Core Inlet Flow Distribution in the APR-Type Reactor Under Various Operating Conditions | Sungman Son, Won Man Park, and Choengryul Choi (Elsoltec), Uiju Jeong (KHNP CRI) | PDF보기 | - |
| 2023-Autumn | 5G : 원자력열수력 (Nuclear Thermal Hydraulics) | 10.26(Thu) 13:00 | Lobby (3F) | Preliminary Mass and Energy Release Analysis for Postulated MSLB Accidents on APR1400 Using SPACE-ME Methodology | Jisu Kim, Seong Ho Jee, Sung Yong Kim, Min Shin Jung, Eun Ju Lee, and Seok Jeong Park(KEPCO E&C) | PDF보기 | PPT보기 |
| 2023-Autumn | 5G : 원자력열수력 (Nuclear Thermal Hydraulics) | 10.26(Thu) 13:00 | Lobby (3F) | Assessment of the Emergency Operating Procedures for Main Steam Line Break Accident of the OPR1000 Nuclear Reactor using the MARS Code | Chae Bon Gu, Min Gi Kim, and Jae Jun Jeong(PNU) | PDF보기 | - |
Last Modified : 1998-Autumn
