학술발표회 논문집
| Year | Div | Date/Time | ROOM | Title | Author | Abstract File | Presentation File |
|---|---|---|---|---|---|---|---|
| 2016-Spring | 4A : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.12(Thu) 12:20 | 301 (3F) | Fretting Wear Behavior of ATF Cladding against Surface-Treated Spacer Grids | Young-Ho Lee, Il-Hyun Kim, Jung-Hwan Park, Hyun-Gil Kim, and Hyung-Kyu Kim(KAERI) | PDF보기 | - |
| 2016-Spring | 4B : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.12(Thu) 09:00 | 302 (3F) | (초청발표1)Research on Materials Degradation in Reactor Internals of PWRs | Seong Sik Hwang, Yun Soo Lim, Dong Jin Kim, Sung Woo Kim, Min Jae Choi, Hyung Ha Jin, and Hong Pyo Kim(KAERI) | - | - |
| 2016-Spring | 4B : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.12(Thu) 09:30 | 302 (3F) | (초청발표2)Research on SCC Initiation of Welds: Experiments and Modeling | Jae Phil Park, Won Dong Park, and Chi Bum Bahn(PNU) | - | - |
| 2016-Spring | 4B : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.12(Thu) 10:00 | 302 (3F) | Surface and Grain Boundary Oxidation of Ni-Based Alloys in Hydrogenated Water | Yun Soo Lim, Seong Sik Hwang, and Sung Woo Kim(KAERI) | PDF보기 | - |
| 2016-Spring | 4B : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.12(Thu) 10:20 | 302 (3F) | Investigation on the Fracture behavior of Piping Materials under Seismic Loading Condition | Myung Rak Cho and Jin Weon Kim(CSU), Yun Jae Kim(KU) | PDF보기 | - |
| 2016-Spring | 4B : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.12(Thu) 11:00 | 302 (3F) | Phase-field modeling of Mn-Ni-Si precipitate behavior on the bcc-Fe matrix | Kunok Chang and Junhyun Kwon(KAERI) | PDF보기 | - |
| 2016-Spring | 4B : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.12(Thu) 11:20 | 302 (3F) | Thermal Aging Effects on Heat Affected Zone of Alloy 600 in Dissimilar Metal Weld | Junhyuk Ham, Kyoung Joon Choi, Seung Chang Yoo, and Ji Hyun Kim(UNIST) | PDF보기 | - |
| 2016-Spring | 4B : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.12(Thu) 11:40 | 302 (3F) | Development of Deterministic and Probabilistic Fracture Mechanics Analysis Code PROFAS-RV for Reactor Pressure Vessel ? Progress of the Work | Jong-Min Kim and Bong-Sang Lee(KAERI) | PDF보기 | - |
| 2016-Spring | 4B : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.12(Thu) 12:00 | 302 (3F) | Hydrothermal Corrosion and Degradation of Mechanical Properties of Silicon Carbide and Its Composites | Daejong Kim, Hyeon-Geun Lee, Ji Yeon Park, and Weon-Ju Kim(KAERI) | PDF보기 | - |
| 2016-Spring | 4C : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.13(Fri) 09:00 | 301 (3F) | (초청발표1)Development and Implementation HANA Cladding for PWR | Jong Sung Yoo, Yoon Ho Kim, Yong Kyoon Mok, and Jae Ik Kim(KEPCO NF) | - | - |
| 2016-Spring | 4C : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.13(Fri) 09:30 | 301 (3F) | Development of Deterministic and Probabilistic Fracture Mechanics Analysis Code PROFAS-RV for Reactor Pressure Vessel-Progress of the Work | Kyu-Tae Kim(DU) | PDF보기 | - |
| 2016-Spring | 4C : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.13(Fri) 10:00 | 301 (3F) | Rethinking the Zircaloy Embrittlement Criteria and Its Impact on the Safety Margin | Youho Lee, Bokyung Kim, and Hee Cheon No(KAIST) | PDF보기 | - |
| 2016-Spring | 4C : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.13(Fri) 10:20 | 301 (3F) | Status of LOCA Performance Tests of HANA-6 Cladding | Hun Jang, Sung Yong Lee, Dae Gyun Ko, Min Young Choi, Yoon Ho Kim, and Yong Kyoon Mok(KEPCO NF) | PDF보기 | - |
| 2016-Spring | 4C : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.13(Fri) 11:00 | 301 (3F) | Interaction Behavior between Binary Lanthanide Alloy and HT9 | Jun Hwan Kim, Jin Sik Cheon, Byoung Oon Lee, and June Hyung Kim(KAERI) | PDF보기 | - |
| 2016-Spring | 4C : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.13(Fri) 11:20 | 301 (3F) | Simulated Transient Behavior of Fuel Cladding of SFR | Sang Hun Shin, Jun Hwan Kim, June-Hyung Kim, Woo Seog Ryu, Sang Gyu Park, and Sung Ho Kim(KAERI) | PDF보기 | - |
Last Modified : 1998-Autumn
