학술발표회 논문집 (ISSN: 3140-1864)
| Year | Div | Date/Time | ROOM | Title | Author | Abstract File | Presentation File |
|---|---|---|---|---|---|---|---|
| 2021-Spring | 5A : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.13(Thu) 14:10 | On-line | Thermal Performance Test Facility for Nuclear Battery from a Conventional Dry Cask Using Hybrid Heat Pipe | Dong Hun Lee and In Cheol Bang(UNIST) | PDF보기 | - |
| 2021-Spring | 5A : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.13(Thu) 14:30 | On-line | Gas Stratification and Condensation Heat Transfer in Steam-Air-Helium Mixture | Il Woong Park, In Yeop Kang, Sang Min Song, Si Hyuk Yang, Hyun Jin Yong, and Yeon-Gun Lee(JNU) | PDF보기 | - |
| 2021-Spring | 5A : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.13(Thu) 14:50 | On-line | Natural and Forced Convection Heat Transfer of Single Heating Sphere in a Packed Bed | Je-Young Moon, Seong-Il Baek, and Bum-Jin Chung(KHU) | PDF보기 | - |
| 2021-Spring | 5A : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.13(Thu) 15:10 | On-line | Natural Convection Heat Transfer of the Packed Bed Varying the Bed Height and Sphere Diameter | Hyun-Ha Ahn, Je-Young Moon, Dong-Hyuk Park, and Bum-Jin Chung(KHU) | PDF보기 | - |
| 2021-Spring | 5A : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.13(Thu) 15:30 | On-line | Fluidelastic Instability of Staggered Tube Arrays with Preferentially Flexible Direction to Single Phase Cross Flow: Typical Results | Kang-Hee Lee, Heung-Seok Kang, Dong-Seok Oh, Chan Lee, Tae-Hyun Chun, Ik-Sung Im, Chang-Hwan Shin, Sung-Wook Lee, and Soo-Ho Kim(KAERI), Jong-In Kim, Chang-Hoon Ha, Doo-Ho Hong, and Min-Ki Cho(DOOSAN) | PDF보기 | - |
| 2021-Spring | 5A : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.13(Thu) 15:50 | On-line | Effects of Chromium-based Accident Tolerant Fuel Coating on Rewetting Temperature under Reflood Condition | Doyoung Shin, Namgook Kim, Joonyoung Bae, and Sung Joong Kim(HYU) | PDF보기 | - |
| 2021-Spring | 5B : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.14(Fri) 09:00 | On-line | Hydraulic Characteristic of Two-Phase Natural Circulation Loop as PCCS and Visualization | Sun Taek Lim, Koung Moon Kim, and Ho Seon Ahn(INU), Dong-Wook Jerng(CAU) | PDF보기 | - |
| 2021-Spring | 5B : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.14(Fri) 09:20 | On-line | Natural Convection Phenomena of the Air in the Vertical Parallel Plates under High Wall Temperature Conditions | Koung Moon Kim, Sun Taek Lim, and Ho Seon Ahn(INU), Dong-Wook Jerng(CAU) | PDF보기 | - |
| 2021-Spring | 5B : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.14(Fri) 09:40 | On-line | Test Result on a Small Break Loss-of-Coolant Accident Simulation for the Control Rod Driving Mechanism Nozzle Rupture with a Failure of Safety Injection Pump using the ATLAS Facility | Jae bong Lee, Byoung-Uhn Bae, Yusun Park, Jongrok Kim, Seok Cho, Nam Hyun Choi, and Kyoung-Ho Kang(KAERI) | PDF보기 | - |
| 2021-Spring | 5B : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.14(Fri) 10:00 | On-line | Experimental Study on the Intermediate Break Loss of Coolant Accident (IBLOCA) with Total failure of Safety Injection Pumps | Yusun Park, Byoung Uhn Bae, Jongrok Kim, Jae Bong Lee, Seok Cho, Nam Hyun Choi, and Kyoung Ho Kang(KAERI) | PDF보기 | - |
| 2021-Spring | 5B : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.14(Fri) 10:20 | On-line | Influence of the Mass flux, Inclination and Void Fraction on the Flow Boiling CHF using a Hydrogen Evolution System | Jeong-Won Han, Hae-Kyun Park, and Bum-Jin Chung(KHU) | PDF보기 | - |
| 2021-Spring | 5B : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.14(Fri) 10:40 | On-line | Natural Convection Heat Transfer of Two Heating Spheres with Pitch-to-diameter Ratio | Seong-Il Baek, Je-Young Moon, Dong-ho Shin, and Bum-Jin Chung(KHU) | PDF보기 | PPT보기 |
| 2021-Spring | 5B : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.14(Fri) 11:00 | On-line | Heat Transfer Surface Morphology and Oxidation Effect on the CHF under Vertical Flow Boiling Considering the RPV Manufacturing and Operating Condition | Jun Yeong Jung, Min Suk Lee, and Yong Hoon Jeong(KAIST) | PDF보기 | - |
| 2021-Spring | 5B : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.14(Fri) 11:20 | On-line | Commissioning Test of NEOUL-R Facility Designed for Critical Heat Flux Measurement under Rolling Motion | Geon-Woo Kim, Jin-Seong Yoo, Heepyo Hong, Goon-Cherl Park, and Hyoung Kyu Cho(SNU) | PDF보기 | - |
| 2021-Spring | 5C : 원자력열수력 (Nuclear Thermal Hydraulics) | 5.13(Thu) 09:00 | On-line | Analysis of Reactor Pressure Vessel Upper Head SBLOCA+LSI at the ATLAS Experimental Facility using the MARS-KS 1.5 | Hyunjoon Jeong and Taewan Kim(INU) | PDF보기 | - |
Last Modified : 1998-Autumn
