학술발표회 논문집
| Year | Div | Date/Time | ROOM | Title | Author | Abstract File | Presentation File |
|---|---|---|---|---|---|---|---|
| 2022-Spring | 5I : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.19(Thu) 13:00 | 로비 (3F) | Preliminary Study for Reactor Kinetics Modeling | Seung Chan LEE(KHNP) | PDF보기 | - |
| 2022-Spring | 5I : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.19(Thu) 13:00 | 로비 (3F) | Wall-modelled LES of the Turbulent Flow in a Nuclear Fuel Rod Bundle | Ye Jun Lee and Jungwoo Kim(SEOULTEC) | PDF보기 | - |
| 2022-Spring | 5I : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.19(Thu) 13:00 | 로비 (3F) | CFD Modeling for Reactor Coolant System Natural Circulation Applied with a Tube Simplification Technique | Dae Kyung Choi and Choengryul Choi(Elsoltec), Kukhee Lim and Yong Jin Cho(KINS) | PDF보기 | - |
| 2022-Spring | 5I : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.19(Thu) 13:00 | 로비 (3F) | Preliminary CFD Study of Pressure Drop in Helical Tube Steam Generator for SMR Application | Doh Hyeon Kim and Jeong Ik Lee(KAIST) | PDF보기 | - |
| 2022-Spring | 5I : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.19(Thu) 13:00 | 로비 (3F) | Implementation of New Condensation Model into the CAP Code | Kum Ho Han, Jehee Lee, Yeon Jun Choo, and Soon Joon Hong(FNC Tech.) | PDF보기 | - |
| 2022-Spring | 5I : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.19(Thu) 13:00 | 로비 (3F) | Study on the Size of Printed Circuit Heat Exchangers for a Pool-type Research Reactor | Seongmin Lee, In Guk Kim, Hong Beom Park, and Kyoung Woo Seo(KAERI) | PDF보기 | - |
| 2022-Spring | 5I : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.19(Thu) 13:00 | 로비 (3F) | Effect of Virtual Mass Coefficient on Critical Flow Model for S-CO2 System | Jae Jun Lee and Jeong Ik Lee(KAIST) | PDF보기 | - |
| 2022-Spring | 5I : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.19(Thu) 13:00 | 로비 (3F) | Numerical Analysis of Vortical Flow Structure for 61-pin Wire-Wrapped Fuel Assembly | Seong Bin Hong and Jae Ho Jeong(Gachon Univ.) | PDF보기 | - |
| 2022-Spring | 5I : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.19(Thu) 13:00 | 로비 (3F) | Evaluation on Effect of Heat Transfer Change by Cr-coated Cladding for Large Break-Loss of Coolant Accident | Jae-Ho Bae, Soon-Joon Hong, Beop-Dong Jeong, and Tae-Sun Ro(FNC Tech.) | PDF보기 | - |
| 2022-Spring | 5I : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.19(Thu) 13:00 | 로비 (3F) | Assessment of SLTHEN Code Estimation Capability for the Coolant Temperature Distribution using the RANS Based CFD Analysis | Junkyu Han and Jonggan Hong(KAERI), Jaehyoung Jun(JH solution) | PDF보기 | - |
| 2022-Spring | 5I : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.19(Thu) 13:00 | 로비 (3F) | Status of Optimal Evaluation System for Safety Analysis OPR1000 and Westinghouse Nuclear Power Plants | Bum-Soo Youn and Yo-Han Kim(KHNP) | PDF보기 | - |
| 2022-Spring | 6A : 원자력 안전 (Nuclear Safety) | 5.19(Thu) 09:00 | 202호 (2F) | A Study on Intensive QA Inspection using Information from Risk-Informed Classification of SSCs | Ju Sang Cho and Hak Kyu Lim(KINGS) | PDF보기 | - |
| 2022-Spring | 6A : 원자력 안전 (Nuclear Safety) | 5.19(Thu) 09:20 | 202호 (2F) | The Sensitivity Analysis Without Credit to Operator Action for 30 Minutes in the APR1000 PSA | Jaegab Kim, Ho Seok, Jeongguk Song, Inchul Ryu, and Jinkyoo Yoon(KEPCO E&C),\nJiyong Oh(KHNP) | PDF보기 | - |
| 2022-Spring | 6A : 원자력 안전 (Nuclear Safety) | 5.19(Thu) 09:40 | 202호 (2F) | Probability Subtraction Method Implementation into SAREX | Dong Kyu Kim, Sang Hyun Kim, and Ho Seok(KEPCO E&C), Seong Kyu Park(NESS) | PDF보기 | PPT보기 |
| 2022-Spring | 6A : 원자력 안전 (Nuclear Safety) | 5.19(Thu) 10:00 | 202호 (2F) | A Framework for the Applications of a Reduced Order Model to Enhance the Safety of Nuclear Power Plants in Terms of PSA | Kyungho Jin, Hyeonmin Kim, and Jinkyun Park(KAERI) | PDF보기 | - |
Last Modified : 1998-Autumn
