학술발표회 논문집
| Year | Div | Date/Time | ROOM | Title | Author | Abstract File | Presentation File |
|---|---|---|---|---|---|---|---|
| 2018-Autumn | 4A : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 10.25(Thu) 09:40 | 컨퍼런스홀3 (1F) | Development Status of Accident Tolerant Fe-based Alloy Cladding at KEPCO NF (in Collaboration with KAIST) | Hun Jang, Sung Yong Lee, Dae Gyun Ko, Min Young Choi, Chae-ho Lim, Yoon Ho Kim, Yong Kyoon Mok, and Seung Jae Lee(KEPCO NF), Hyunmyung Kim, Chaewon Kim, and Changheui Jang(KAIST) | PDF보기 | - |
| 2018-Autumn | 4A : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 10.25(Thu) 10:00 | 컨퍼런스홀3 (1F) | Microstructure and Mechanical Properties of Fe-base alloys as Potential Accident Tolerant Fuel Cladding Materials | Hyunmyung Kim, Chaewon Kim, Gokul Obulan Subramanian, Suhyun Park, and Changheui Jang(KAIST) | PDF보기 | - |
| 2018-Autumn | 4A : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 10.25(Thu) 10:40 | 컨퍼런스홀3 (1F) | Design and Evaluation of Advanced Ferritic Steel for Accident Tolerant Fuel Cladding | Sung Yong Lee, Hun Jang, Jun Sik Lee, Dae Gyun Ko, Min Young Choi, Yoon Ho Kim, Yong Kyoon Mok, and Seung Jae Lee(KEPCO NF) | PDF보기 | - |
| 2018-Autumn | 4A : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 10.25(Thu) 11:00 | 컨퍼런스홀3 (1F) | Deformation and Fracture Behaviors of Fe-Based Claddings for Accident-Tolerant Fuel under Fretting Wear Condition | Young-Ho Lee, Dong-Jun Park, Jung-Hwan Park, Yang-Il Jung, Il-Hyun Kim, Byung-Kwon Choi, and Hyun-Gil Kim(KAERI) | PDF보기 | - |
| 2018-Autumn | 4A : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 10.25(Thu) 11:20 | 컨퍼런스홀3 (1F) | Characterization of the Thermal Conductivities of Molybdenum Metal Particles Aligned UO2 Fuel Pellets | Dong Seok Kim, Dong-Joo Kim, Sang-Chae Jeon, Jang Soo Oh, Keon Sik Kim, Jong Hun Kim, and Jae Ho Yang(KAERI) | PDF보기 | - |
| 2018-Autumn | 4A : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 10.25(Thu) 11:40 | 컨퍼런스홀3 (1F) | Cumulative Damage Fraction as a SFR Fuel Design Criterion | Jin-Sik Cheon, June-Hyung Kim, Byoung-Oon Lee, and Chan-Bock Lee(KAERI) | PDF보기 | - |
| 2018-Autumn | 4B : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 10.25(Thu) 09:00 | 세미나2 (B1F) | Development of Containment Liner Plate Corrosion Damage Control Technology in Nuclear Power Plant | Min-Bum Heo, Hyun-Chul Lee, Dong-Seok Kim, and Young-Jin Kim (FNC Tech.) | PDF보기 | - |
| 2018-Autumn | 4B : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 10.25(Thu) 09:20 | 세미나2 (B1F) | Oxidation Behavior of Ni-Cr-Fe Alloys with Different Cr Content in Simulated PWR Primary Water | Hee-Sang Shim and Do Haeng Hur(KAERI) | PDF보기 | - |
| 2018-Autumn | 4B : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 10.25(Thu) 09:40 | 세미나2 (B1F) | Environmental Barrier Coatings Development for SiCf /SiC Composite-Based Fuel Cladding Applications | Daejong Kim, Jung Ho Shin, Hyun-Geun Lee, Ji Yeon Park, and Weon-Ju Kim(KAERI) | PDF보기 | - |
| 2018-Autumn | 4B : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 10.25(Thu) 10:00 | 세미나2 (B1F) | Combined Effects of Magnetite and Sulfur Oxyanions on the Corrosion Behavior of Alloy 600 | Jeoh Han, Geun Dong Song, Soon-Hyeok Jeon, and Do Haeng Hur(KAERI), Jong Hyeon Lee(CNU) | PDF보기 | - |
| 2018-Autumn | 4B : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 10.25(Thu) 10:40 | 세미나2 (B1F) | Evaluation of Mechanical Properties of Helium Implanted Inconel X-750 Alloys Using Micro Bending Test | Hyung-Ha Jin, I Seul Ryu, Junhyun Kwon, and Gyeong-Geun Lee(KAERI) | PDF보기 | - |
| 2018-Autumn | 4B : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 10.25(Thu) 11:00 | 세미나2 (B1F) | CRUD Deposition Experiment in Simulated PWR Primary Water Chemistry | Yunju Lee, Seungchang Yoo, and Ji Hyun Kim(UNIST), Byung Gi Park(SCHU) | PDF보기 | - |
| 2018-Autumn | 4B : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 10.25(Thu) 11:20 | 세미나2 (B1F) | Calculation of Solution Energy of Oxygen Impurity in Liquid Na by Atomistic Simulations | Junhyoung Gil and Takuji Oda(SNU) | PDF보기 | - |
| 2018-Autumn | 4B : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 10.25(Thu) 11:40 | 세미나2 (B1F) | Derivation of Circumferential Tensile Property of Alloy 690 Steam Generator Tube Using Inverse Analysis Method | Jongmin Kim, Seokmin Hong, Minchul Kim, and Semi Hyun(KAERI) | PDF보기 | - |
| 2018-Autumn | 4B : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 10.25(Thu) 12:00 | 세미나2 (B1F) | Bayesian Statistical Analysis on the In-reactor Diametral Creep of Pressure Tubes in Wolsong Units | Gyeong-Geun Lee, Dong-Hyun Ahn, Hyung-Ha Jin, Junhyun Kwon, and Jong Yeob Jung(KAERI), Gang Hoo Kim(KAIST) | PDF보기 | - |
Last Modified : 1998-Autumn
