학술발표회 논문집
| Year | Div | Date/Time | ROOM | Title | Author | Abstract File | Presentation File |
|---|---|---|---|---|---|---|---|
| 2024-Spring | 5H : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.9(Thu) 13:00 | Lobby (3F) | Preliminary CFD Analysis for the Rotating Cavitation Flow inside a Centrifugal Pump | Gong Hee Lee(KINS), Yong Kab Lee(SIMEX) | PDF보기 | - |
| 2024-Spring | 5H : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.9(Thu) 13:00 | Lobby (3F) | Numerical Prediction of DNB under Vertical and Inclined Condition with R134a Refrigerant | Giwon Bae and Hyoung kyu Cho(SNU) | PDF보기 | - |
| 2024-Spring | 5H : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.9(Thu) 13:00 | Lobby (3F) | Critical Flow Prediction by Direct Solving of Characteristic Equations | Kwi Seok Ha, Jaeseok Heo, Jonghyuk Lee, and Kyung Doo Kim(KAERI) | PDF보기 | - |
| 2024-Spring | 5H : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.9(Thu) 13:00 | Lobby (3F) | Coupling of CUPID Subchannel Module with Neutron Kinetics Code and Fuel Performance Code for Pin-Wise Multi-physics | Yeonghun Lee, Kyuseok Sim, Youho Lee, Jae Ryong Lee(KAERI), Hyoung Kyu Cho(SNU) | PDF보기 | - |
| 2024-Spring | 5H : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.9(Thu) 13:00 | Lobby (3F) | Exploring Two-Phase Flow Instabilities in Helical Steam Generators Using MARS-KS Code | Seunghwan Oh, Doh Hyeon Kim, and Jeong Ik Lee(KAIST) | PDF보기 | - |
| 2024-Spring | 5H : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.9(Thu) 13:00 | Lobby (3F) | Validation of SPACE-CAP Codes for Coupling the RCS and Containment Systems with OECD-ATLAS3 C1.2 Test | Byoung Uhn Bae, Jae Bong Lee, Yusun Park, Seok Cho, and Kyoung Ho Kang(KAERI) | PDF보기 | - |
| 2024-Spring | 5H : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.9(Thu) 13:00 | Lobby (3F) | Development of Thermal Analysis Module of MSRE Core for Monte Carlo Neutron Transport Code | Min Seo Son, Moon Hee Choi, and Hyoung Kyu Cho(SNU) | PDF보기 | - |
| 2024-Spring | 5H : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.9(Thu) 13:00 | Lobby (3F) | Prediction on Mixed Convection Sodium Flow using MULTID Component Model of the MARS-LMR Code | Jae-Ho Bae(KAERI), Hae-Yong Jeong(Sejong Univ.) | PDF보기 | - |
| 2024-Spring | 5H : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.9(Thu) 13:00 | Lobby (3F) | Adequacy Results of 2nd Exercise in OECD/NEA ATRIUM Project for SPACE | Chiwoong CHOI, Jaeseok Heo, and Seungwook Lee(KAERI) | PDF보기 | - |
| 2024-Spring | 5H : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.9(Thu) 13:00 | Lobby (3F) | Sizing Orifice for Sustaining Flow Instability of a Steam Generator in NuScale SMR | Hee Joon Lee(Kookmin Univ.), Youngmin Bae(KAERI) | PDF보기 | - |
| 2024-Spring | 5H : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.9(Thu) 13:00 | Lobby (3F) | Effect of CCFL in Upper Plenum for ATLAS DVI Line Break Test | Hae Min Park and Seung Wook Lee(KAERI) | PDF보기 | - |
| 2024-Spring | 5H : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.9(Thu) 13:00 | Lobby (3F) | CFD Investigation on Sagging Effects in CANDU Reactors | Jin Yoo(Chungnam National Univ.|NESS), Chul-Kyu Lim, Hyun-Sik Kang, Hyeon-Sik Chang, Han-Rim Choi,\nChang-Sup Lee, Hyun-Woo Park, Beom-Seock Kim, Seong-Kyu Park, Chul-Jin Choi, Chang-Sok Cho,\nand Mi-Suk Jang(NESS), Byoung-Jae Kim(Chungnam National Univ.) | PDF보기 | - |
| 2024-Spring | 5H : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.9(Thu) 13:00 | Lobby (3F) | Predictive Model for Entrainment Limitation in Non-Condensable Gas Pressurized Thermosyphon | Benrico Fredi Simamora, Jiyong Kim, and Jaeyoung Lee(Handong Global Univ.) | PDF보기 | - |
| 2024-Spring | 5I : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.9(Thu) 13:00 | Lobby (3F) | LBLOCA ME Release and Containment PT Analysis using KIMERA Methodology for APR1000 | Sung Yong Kim, Jisu Kim, Seong Ho Jee, Min Shin Jung, Eun Ju Lee, and Seok Jeong Park(KEPCO E&C) | PDF보기 | - |
| 2024-Spring | 5I : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.9(Thu) 13:00 | Lobby (3F) | Analysis of Main Steam Line Break and Induced Steam Generator Tube Rupture Accident Using SPACE Code for OPR1000 | Chang-Keun Yang and MinJeong Kim(KHNP CRI) | PDF보기 | - |
Last Modified : 1998-Autumn
