학술발표회 논문집
| Year | Div | Date/Time | ROOM | Title | Author | Abstract File | Presentation File |
|---|---|---|---|---|---|---|---|
| 2022-Autumn | 5F : 원자력열수력 (Nuclear Thermal Hydraulics) | 10.20(Thu) 13:00 | 컨벤션홀I (3F) | Comparison of Two-phase Flow Pressure Drop in Helical Pipe and Straight Pipe Through CFD Analysis | Doh Hyeon Kim, Seunghwan Oh, and Jeong Ik Lee(KAIST), Il Suk Lee(KINS) | PDF보기 | - |
| 2022-Autumn | 5G : 원자력열수력 (Nuclear Thermal Hydraulics) | 10.20(Thu) 13:00 | 컨벤션홀I (3F) | Inclination and Rolling Motion Effect on Subcooled Flow Boiling Pressure Drop Through Annulus Channel with Helical Finned Heater | Hyukjae Ko, Chang Won Lee, Jin-Seoung Yoo, Heepyo Hong, Ja Hyun Ku, Goon-Cherl Park, and Hyoung Kyu Cho(SNU) | PDF보기 | PPT보기 |
| 2022-Autumn | 5G : 원자력열수력 (Nuclear Thermal Hydraulics) | 10.20(Thu) 13:00 | 컨벤션홀I (3F) | Study on the Velocity Distribution of Turbulent Steam Jet from the Non-Circular Nozzle Exit | Jaewon Myeong, Hyeon Gyeom Kim, and Weon Gyu Shin(CNU) | PDF보기 | - |
| 2022-Autumn | 5G : 원자력열수력 (Nuclear Thermal Hydraulics) | 10.20(Thu) 13:00 | 컨벤션홀I (3F) | Local Reverse Heat Transfer of Condensation Heat Exchanger with Non-condensable Gas | Jin-Hwa Yang, Tae-Hwan Ahn, Hwang Bae, and Hyun-Sik Park(KAERI) | PDF보기 | - |
| 2022-Autumn | 5G : 원자력열수력 (Nuclear Thermal Hydraulics) | 10.20(Thu) 13:00 | 컨벤션홀I (3F) | Applying Supervised Learning Algorithm to Nuclear Power Plant Severe Accident Data Generated from MAAP Code | Seok Ho Song and Jeong Ik Lee(KAIST) | PDF보기 | - |
| 2022-Autumn | 5G : 원자력열수력 (Nuclear Thermal Hydraulics) | 10.20(Thu) 13:00 | 컨벤션홀I (3F) | Evaluation of the Effect of Fuel Relocation on the current LBLOCA Safety Analysis using SPACE | Hyungsuk Lee, Tae Beom Lee, and Sang Ik Lee(KEPCO NF) | PDF보기 | - |
| 2022-Autumn | 5G : 원자력열수력 (Nuclear Thermal Hydraulics) | 10.20(Thu) 13:00 | 컨벤션홀I (3F) | Feasibility Study of Wall Temperature Measurement Method using Temperature-Sensitive Fluorescent Material for Application to High-Pressure Flow Boiling Experiment | Woojien Lee, Jonghwi Choi, Ahyeong Cho, and Hyungdae Kim(KHU) | PDF보기 | - |
| 2022-Autumn | 5G : 원자력열수력 (Nuclear Thermal Hydraulics) | 10.20(Thu) 13:00 | 컨벤션홀I (3F) | Primary PFHE Design for Chloride Based Molten Salt Fast Reactor | Sunghyun Yoo, In Woo Son, Sungwook Choi, and JeongIk Lee(KAIST) | PDF보기 | PPT보기 |
| 2022-Autumn | 6A : 원자력 안전 (Nuclear Safety) | 10.20(Thu) 09:00 | 600B호 (6F) | Benchmarking of PHEBUS FPT0 Experiment by using CINEMA and MELCOR Code | Chang Hyun Song, Joon Young Bae, Wonjun Choi, and Sung Joong Kim(HYU), Donggun Son and Jun-Ho Bae(KAERI) | PDF보기 | - |
| 2022-Autumn | 6A : 원자력 안전 (Nuclear Safety) | 10.20(Thu) 09:20 | 600B호 (6F) | A Benchmarking Study for CINEMA and MELCOR Codes Subject to Core Degradation Phase of PHÉBUS FPT 1 by using Dynamic Time Warping | Joon Young Bae, Chang Hyun Song, Wonjun Choi, and Sung Joong Kim(HYU), Donggun Son and Jun-Ho Bae(KAERI) | PDF보기 | - |
| 2022-Autumn | 6A : 원자력 안전 (Nuclear Safety) | 10.20(Thu) 09:40 | 600B호 (6F) | High Temperature Fuel Rod Bundle Analysis of QUENCH-06 Experiment Using CINEMA | Woonho Jeong and Yong Hoon Jeong(KAIST), Dong Gun Son(KAERI) | PDF보기 | - |
| 2022-Autumn | 6A : 원자력 안전 (Nuclear Safety) | 10.20(Thu) 10:00 | 600B호 (6F) | A Preliminary Validation and Sensitivity Analysis of FARO L-14 Experiment using Steam Explosion Module of CINEMA | Seokwon Whang and Hyun Sun Park(SNU), Soon-ho Park(FNC Tech.) | PDF보기 | PPT보기 |
| 2022-Autumn | 6A : 원자력 안전 (Nuclear Safety) | 10.20(Thu) 10:20 | 600B호 (6F) | Validation of OECD CCI-2 Experiment using MCCI Module of CINEMA | Jun Sung Choi and Eung Soo Kim(SNU), Soon Ho Park(FNC Tech.) | PDF보기 | - |
| 2022-Autumn | 6A : 원자력 안전 (Nuclear Safety) | 10.20(Thu) 11:00 | 600B호 (6F) | Application of CINEMA Code to CCI-5 Analysis | Eungsoo Kim and Taehwan Kim(SNU), Soonho Park(FNC Tech.) | PDF보기 | - |
| 2022-Autumn | 6A : 원자력 안전 (Nuclear Safety) | 10.20(Thu) 11:20 | 600B호 (6F) | A Study on Internal PSA for a KAERI Molten Salt Reactor | Kilyoo Kim and SangJi Kim(KAERI) | PDF보기 | - |
Last Modified : 1998-Autumn
