학술발표회 논문집
| Year | Div | Date/Time | ROOM | Title | Author | Abstract File | Presentation File |
|---|---|---|---|---|---|---|---|
| 2016-Spring | 1D : 원자로시스템기술 (Reactor System Technology) | 5.13(Fri) 12:00 | 401B (4F) | Application of Looped Network Analysis Method to Core of Prismatic VHTR | Jeong-Hun Lee, Hyoung-Kyu Cho, and Goon-Cherl Park(SNU) | PDF보기 | PPT보기 |
| 2016-Spring | 1D : 원자로시스템기술 (Reactor System Technology) | 5.13(Fri) 12:20 | 401B (4F) | Calculation of Thermal-Fluid Parameters for the Pre-designed VHTR Core Based on CORONA | Jun Kyu Song, Bong Hyun Cho, Nam-il Tak, and Chang Keun Jo(KAERI) | PDF보기 | - |
| 2016-Spring | 1E : 원자로시스템기술 (Reactor System Technology) | 5.13(Fri) 14:00 | 203 (2F) | (초청발표1) Mechanical Design Features of PGSFR NSSS | Chang-Gyu PARK, Gyeong-Hoi KOO, Jae-Hun CHO, and Sung-Kyun KIM(KAERI) | PDF보기 | - |
| 2016-Spring | 1E : 원자로시스템기술 (Reactor System Technology) | 5.13(Fri) 14:30 | 203 (2F) | Creep-Fatigue Damage Evaluation of a Model Reactor Vessel and Reactor Internals of Sodium Test Facility According to ASME-NH and RCC-MRx Codes | Dong-Won Lim, Hyeong-Yeon Lee, Jae-Hyuk Eoh, Seok-Kwon Son, Jong-Bum Kim, and Ji-Young Jeong(KAERI) | PDF보기 | PPT보기 |
| 2016-Spring | 1E : 원자로시스템기술 (Reactor System Technology) | 5.13(Fri) 14:50 | 203 (2F) | Safety Analysis for Loss of Flow Related to Loss of Off-site Power in PGSFR | Jae-Ho Jeong, Kwi-Lim Lee, Chi-Woong Choi, Tae-Kyung Jeong, and Kwi-Seok Ha(KAERI) | PDF보기 | - |
| 2016-Spring | 1E : 원자로시스템기술 (Reactor System Technology) | 5.13(Fri) 15:30 | 203 (2F) | Performance Evaluation of Sodium-to-Sodium Heat Exchangers in STELLA-2 | Youngchul Jo(KAERI), Seok-kwon Son(KAERI), Jung Yoon(KAERI), and Jiyoung Jeong(KAERI) | PDF보기 | - |
| 2016-Spring | 1E : 원자로시스템기술 (Reactor System Technology) | 5.13(Fri) 15:50 | 203 (2F) | Combined Safety Analysis on Gallium-based Passive Decay Heat Removal System of Ultra-long Cycle Fast Reactor | Seok Bin Seo, In Guk Kim, and In Cheol Bang(UNIST) | PDF보기 | - |
| 2016-Spring | 1E : 원자로시스템기술 (Reactor System Technology) | 5.13(Fri) 16:10 | 203 (2F) | Reactor Vault Cooling System (RVCS) Effect on ULOHS Event for the Prototpe Gen-IV SFR | Chiwoong Choi, Kwiseok Ha, Taekyeong Jeong, Jaeho Jeong, Kwilim Lee, Seungwon Lee, and Sangjun An(KAERI) | PDF보기 | - |
| 2016-Spring | 1E : 원자로시스템기술 (Reactor System Technology) | 5.13(Fri) 16:30 | 203 (2F) | Melt Fragmentation Characteristics of Metal Fuel with Melt Injection Mass during Initiating Phase of SFR Severe Accidents | Hyo Heo, Min Ho Lee, and In Cheol Bang(UNIST), Dong Wook Jerng(CAU) | PDF보기 | - |
| 2016-Spring | 1E : 원자로시스템기술 (Reactor System Technology) | 5.13(Fri) 16:50 | 203 (2F) | Variations in CO Concentration Based on the Control Parameters during Na-CO2 Reaction | Hyun Su Kim, Gunyeop Park, and Hyun Sun Park(POSTECH), Moo Hwan Kim(KINS) | PDF보기 | - |
| 2016-Spring | 1F : 원자로시스템기술 (Reactor System Technology) | 5.12(Thu) 13:00 | 3층 로비 | Development of PC-based Simulator PCTRAN for SMART | Juyoul Kim(FNC Tech.), Li-chi Cliff Po(MST) | PDF보기 | - |
| 2016-Spring | 1F : 원자로시스템기술 (Reactor System Technology) | 5.12(Thu) 13:00 | 3층 로비 | Preliminary Study on the Effect of Pressure Drop due to Spacer Grid in SMRs | Hwa-Young Jung, Min-Gil Kim, and Jeong Ik Lee(KAIST) | PDF보기 | - |
| 2016-Spring | 1F : 원자로시스템기술 (Reactor System Technology) | 5.12(Thu) 13:00 | 3층 로비 | Thermal Behavior of the Coolant in the Emergency Cooldown Tank for an Integral Reactor | Joo Hyung Moon, Seok Kim, Woo Shik Kim, Seo Yoon Jung, and Young In Kim(KAERI) | PDF보기 | - |
| 2016-Spring | 1F : 원자로시스템기술 (Reactor System Technology) | 5.12(Thu) 13:00 | 3층 로비 | Estimation of POL-iteration Method in Fast Running DNBR Code | Hyuk Kwon, Seoung Jin Kim, Kyong Won Seo, and Dae Hyun Hwang(KAERI) | PDF보기 | - |
| 2016-Spring | 1F : 원자로시스템기술 (Reactor System Technology) | 5.12(Thu) 13:00 | 3층 로비 | The Evaluation of the ROP Trip Set Point for the Different CANDU-6 Fuel Type | Young Ae Kim(KHNP CRI) | PDF보기 | - |
Last Modified : 1998-Autumn
