학술발표회 논문집
| Year | Div | Date/Time | ROOM | Title | Author | Abstract File | Presentation File |
|---|---|---|---|---|---|---|---|
| 2016-Spring | 4J : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.12(Thu) 13:00 | 3층 로비 | Stress Analysis of an Alumina Structure for the Sintering of Composite Materials | Jong Han Park, Kwang Jae Son, and Jin Tae Hong(KAERI) | PDF보기 | - |
| 2016-Spring | 4J : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.12(Thu) 13:00 | 3층 로비 | Helium Gas Permeability Evaluation of Triplex Nuclear Fuel Cladding | Hyeon-Geun Lee, Daejong Kim, Ji Yeon Park, and Weon-Ju Kim(KAERI) | PDF보기 | - |
| 2016-Spring | 4J : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.12(Thu) 13:00 | 3층 로비 | The synthesis and characterization of W- 1wt. % TiC alloy using a chemical method | Taehee Kim and Ho Jin Ryu(KAIST) | PDF보기 | - |
| 2016-Spring | 4J : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.12(Thu) 13:00 | 3층 로비 | Magnetic Properties Studies on Thermal Aged Fe-Cu Alloys for? The Simulation of Radiation Damage | Cheol Kyu Lee, Kishore M.B, and Dukgeun Park(KAERI), Derac Son(HNU) | PDF보기 | - |
| 2016-Spring | 4J : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.12(Thu) 13:00 | 3층 로비 | Effects of Proton Irradiation on Compressive Strength of Single-crystalline 6H Silicon Carbide at Room Temperature | Gihyun Kwon and Chansun Shin(MJU), Gwang-Min Sun(KAERI) | PDF보기 | - |
| 2016-Spring | 4J : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.12(Thu) 13:00 | 3층 로비 | Effect of Matrix Grain Size on the Oxidation and Carburization Resistance of Alloy 800HT in High Temperature CO2 Environment | Gokul Obulan Subramanian, Ho Jung Lee, Ji Ho Shin, and Changheui Jang(KAIST) | PDF보기 | - |
| 2016-Spring | 5A : 원자력열수력 및 안전 (Thermal Hydraulics and Safety) | 5.12(Thu) 09:30 | 201A (2F) | (초청발표1)2-Train Passive Safety System Tests for the SMART Design with the SMART-ITL Facility | Hyun Sik Park, Hwang Bae, Sung-Uk Ryu, Byong-Guk Jeon, Hyobong Ryu, Sun-Joon Byun, Nam-Hyun Choi,Yun-Gon Bang, Yong-Cheol Shin, Kyoung-Ho Min, and Sung-Jae Yi(KAERI) | PDF보기 | - |
| 2016-Spring | 5A : 원자력열수력 및 안전 (Thermal Hydraulics and Safety) | 5.12(Thu) 10:00 | 201A (2F) | Improvement of MARS-MultiD on Analysis of ECC Bypass with Newly-developed Friction Models | Jin-Hwa Yang and Dong-Jin Euh(KAERI), Chi-Jin Choi, Hyoung-Kyu Cho, and Goon-Cherl Park(SNU) | PDF보기 | - |
| 2016-Spring | 5A : 원자력열수력 및 안전 (Thermal Hydraulics and Safety) | 5.12(Thu) 10:20 | 201A (2F) | Similarity Assessment of Engineering Designed Small Scaled Sodium Integral Test Facility | Soon-Joon Hong and Yong-Hwy Kim(FNC Tech.), Jewhan Lee and Jae-Hyuk Eoh(KAERI) | PDF보기 | - |
| 2016-Spring | 5A : 원자력열수력 및 안전 (Thermal Hydraulics and Safety) | 5.12(Thu) 11:00 | 201A (2F) | Single-phase Natural Circulation of High-Pr Heat Transfer Simulant oil | Yukyung Shin, Seok Bin Seo, In Guk Kim, and In Cheol Bang(UNIST) | PDF보기 | - |
| 2016-Spring | 5A : 원자력열수력 및 안전 (Thermal Hydraulics and Safety) | 5.12(Thu) 11:20 | 201A (2F) | Experimental Study of Hydraulic Control Rod Drive Mechanism for Passive IN-core Cooling System of Nuclear Power Plant | In Guk Kim, Kyung Mo Kim, Yeong Shin Jeong, and In Cheol Bang(UNIST) | PDF보기 | - |
| 2016-Spring | 5A : 원자력열수력 및 안전 (Thermal Hydraulics and Safety) | 5.12(Thu) 11:40 | 201A (2F) | Experimental Investigation on Thermal-Hydraulic Interaction between CMT and SIT of a Two-Train Passive Safety System during an SBLOCA Test | Hwang Bae, Sung Uk Ryu, Byong-Guk Jeon, Sun-Jun Byun, Hyo Bong Ryu, Yong-Cheol Shin, Kyoung-Ho Min,Jong-Kuk Park, Nam-Hyun Choi, Yun-Gon Bang, Sung-Jae Yi, and Hyun-Sik Park(KAERI) | PDF보기 | - |
| 2016-Spring | 5A : 원자력열수력 및 안전 (Thermal Hydraulics and Safety) | 5.12(Thu) 12:00 | 201A (2F) | Loss of Coolant Accident Simulation for the Top-Slot break at Cold Leg Focusing on the Loop Seal Reformation under Long Term Cooling with the ATLAS | Jongrok Kim, Yusun Park, Byoung-Uhn Bae, Nam-Hyun Choi, Kyoung-Ho Kang, and Ki-Yong Choi(KAERI) | PDF보기 | - |
| 2016-Spring | 5B : 원자력열수력 및 안전 (Thermal Hydraulics and Safety) | 5.12(Thu) 09:30 | 201B (2F) | (초청발표1)A Discussion of Common-Cause Failure in Digital I&C Systems fron the Point of View of Safety Analysis | Gyu Cheon Lee(KEPCO E&C) | - | - |
| 2016-Spring | 5B : 원자력열수력 및 안전 (Thermal Hydraulics and Safety) | 5.12(Thu) 10:00 | 201B (2F) | Effects of the Pressurized Water Reactor Main Steam Line Break Location on the Blowdown Loading | Jong Chull Jo, Soon Ho Kang, and Won Joon Chang(KINS) | PDF보기 | - |
Last Modified : 1998-Autumn
