학술발표회 논문집
| Year | Div | Date/Time | ROOM | Title | Author | Abstract File | Presentation File |
|---|---|---|---|---|---|---|---|
| 2019-Spring | 5G : 원자력 열수력 (Nuclear Thermal Hydraulics) | 5.23(Thu) 13:00 | 로비 (3F) | Experimental Assessment on Main Flow Path and Heat Loss of SMART-ITL Facility during Specific Steady-State Conditions | Hwang Bae, Sung Uk Ryu, Byoung-Guk Jeon, Jin-Hwa Yang, Yong-Cheol Shin, Kyoung-Ho Min, Jong-Kuk Park, Nam-Hyun Choi, Yun-Gun Baeng, Chan-Jong Seo, Sung-Jae Yi, and Hyun-Sik Park(KAERI) | PDF보기 | - |
| 2019-Spring | 5G : 원자력 열수력 (Nuclear Thermal Hydraulics) | 5.23(Thu) 13:00 | 로비 (3F) | Experimental Study on the Cooling Performance of a Rod Type Heat Pipe for Passive Cooling System | Jonghwi Choi and Hyunsik Park(KAERI), Sangmin Park and Hyungdae Kim(KHU) | PDF보기 | - |
| 2019-Spring | 5H : 원자력 열수력 (Nuclear Thermal Hydraulics) | 5.23(Thu) 13:00 | 로비 (3F) | CFD Simulation of Cavitation Flow inside a Square-Edged Orifice using ANSYS CFX | Gong Hee Lee and Jun Ho Bae(KINS) | PDF보기 | - |
| 2019-Spring | 5H : 원자력 열수력 (Nuclear Thermal Hydraulics) | 5.23(Thu) 13:00 | 로비 (3F) | Plant Application of SPACE-mTRAN Coupled Code System | Seung Wook Lee, Hyo Chan Kim, Yong Sik Yang, and Kyung-Doo Kim(KAERI), Jin-Hyuk Hong(EDT) | PDF보기 | - |
| 2019-Spring | 5H : 원자력 열수력 (Nuclear Thermal Hydraulics) | 5.23(Thu) 13:00 | 로비 (3F) | Sensitivity Analysis of Operator Recovery Actions for Multiple Steam Generator Tube Rupture Event in OPR1000 | MinJeong Kim(KHNP CRI) | PDF보기 | - |
| 2019-Spring | 5H : 원자력 열수력 (Nuclear Thermal Hydraulics) | 5.23(Thu) 13:00 | 로비 (3F) | Evaluation of Sensitivity Study on the Reactor Power Effect for Complete Flow Blockages of Plate-type Fuel Assembly | Jong-Pil Park(KAERI) | PDF보기 | - |
| 2019-Spring | 5H : 원자력 열수력 (Nuclear Thermal Hydraulics) | 5.23(Thu) 13:00 | 로비 (3F) | Extension of the SPACE Code Capability into Thermal-Hydraulic Analysis for Ocean Nuclear Reactor | Byoung Jae Kim and Young Seock An(CNU), Seung Wook Lee(KAERI) | PDF보기 | - |
| 2019-Spring | 5H : 원자력 열수력 (Nuclear Thermal Hydraulics) | 5.23(Thu) 13:00 | 로비 (3F) | Numerical Demonstration of an Unmanned Reactor Based on Passive Infinite Cooling System | Byoung Jae Kim and Nam Kyu Ryu(CNU), Sung Jae Yi(KAERI) | PDF보기 | - |
| 2019-Spring | 5H : 원자력 열수력 (Nuclear Thermal Hydraulics) | 5.23(Thu) 13:00 | 로비 (3F) | CFD Analysis of Steam Flow at TI-SGTR Accident Induced by MSSV Stuck-Open Faults | Wung Jae Wang and Man Sung Yim(KAIST) | PDF보기 | - |
| 2019-Spring | 5H : 원자력 열수력 (Nuclear Thermal Hydraulics) | 5.23(Thu) 13:00 | 로비 (3F) | Model Development for Condensate Collection from Passive Containment Cooling System and Return to In-Containment Refueling Water Storage Tank | Jin Chul Kang, Jong ho Kim, and Jae sik Jeung(KEPCO E&C) | PDF보기 | - |
| 2019-Spring | 5H : 원자력 열수력 (Nuclear Thermal Hydraulics) | 5.23(Thu) 13:00 | 로비 (3F) | Void Fraction Predictability of System Codes Based on PSBT Bundle Test | Yunseok Lee, Yeongjae Lee, and Taewan Kim(INU) | PDF보기 | - |
| 2019-Spring | 5H : 원자력 열수력 (Nuclear Thermal Hydraulics) | 5.23(Thu) 13:00 | 로비 (3F) | Computational Analysis of Wall Condensation in the Presence of Non-condensable Gas Mixture Containing a Light Gas with CUPID | Chang Won Lee and Hyoung Kyu Cho(SNU) | PDF보기 | - |
| 2019-Spring | 5H : 원자력 열수력 (Nuclear Thermal Hydraulics) | 5.23(Thu) 13:00 | 로비 (3F) | Preliminary Assessment of SPACE Code for Loss of Ultimate Heat Sink in OPR1000 | Doo-hyuk Kang and Jae-seung Suh(SENTECH) | PDF보기 | - |
| 2019-Spring | 5H : 원자력 열수력 (Nuclear Thermal Hydraulics) | 5.23(Thu) 13:00 | 로비 (3F) | Application of Adjoint Based Node Optimization Method to MARS | Jae Jun Lee, Min-Gil Kim, Seongmin Son, and Jeong Ik Lee(KAIST) | PDF보기 | - |
| 2019-Spring | 5H : 원자력 열수력 (Nuclear Thermal Hydraulics) | 5.23(Thu) 13:00 | 로비 (3F) | Coupling of FLUENT and ANLHTP for Steady-state Thermal Analysis of a Heat Pipe Cooled Reactor Core | San Lee and Hyoung Kyu Cho(SNU), Changho Lee and Taek K. Kim(ANL) | PDF보기 | - |
Last Modified : 1998-Autumn
