학술발표회 논문집
| Year | Div | Date/Time | ROOM | Title | Author | Abstract File | Presentation File |
|---|---|---|---|---|---|---|---|
| 2021-Spring | 4A : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.13(Thu) 10:40 | On-line | TRANOX: Mechanistic Model for Non-Isothermal Steam Oxidation of Zircaloy Cladding | Dongju Kim, Hyunwoo Yook, Kyunghwan Keum , and Youho Lee(SNU) | PDF보기 | - |
| 2021-Spring | 4A : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.13(Thu) 11:05 | On-line | Post-Quench Ductility Test on Pre-hydrided Zr-Nb Cladding and Review on ECCS Criteria | Kyunghwan Keum and Youho Lee(SNU) | PDF보기 | - |
| 2021-Spring | 4B : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.13(Thu) 13:30 | On-line | Effect of Stress Type on the Oxide Layer Properties of Alloy 600MA and 690TT in Simulated Secondary Water | Byung Joon Bae, Jeoh Han, and Do Haeng Hur(KAERI), Jongsup Hong(Yonsei Univ.) | PDF보기 | - |
| 2021-Spring | 4B : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.13(Thu) 13:55 | On-line | Influences of Zn Concentration on the General Corrosion Behavior of Alloy 690TT in Simulated Primary Water of PWRs | Soon-Hyeok Jeon, Dong-Seok Lim, and Do Haeng Hur(KAERI), Jinsoo Choi and Kyu Min Song(KHNP) | PDF보기 | - |
| 2021-Spring | 4B : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.13(Thu) 14:20 | On-line | Novel Test Method to Measure PWSCC Initiation Time of Nickel Alloys Using Rupture Disk-Type Specimen | Sung-Woo Kim, Geon-Woo Jeon, and Dong-Jin Kim(KAERI) | PDF보기 | - |
| 2021-Spring | 4B : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.13(Thu) 14:45 | On-line | Low Cycle Fatigue Life of Alloy 52M Weld Metal in Simulated PWR Environment | junhyuk Ham, seung chang Yoo, yunju Lee, daehyeon Park, and ji hyun Kim(UNIST) | PDF보기 | - |
| 2021-Spring | 4B : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.13(Thu) 15:10 | On-line | Estimation of Creep Behavior of Alloy 690 based on the Power Law Creep Models | Bong-Sang Lee, Jong-Min Kim, June-Yeop Kwon, Kwon-Jae Choi, and Min-Chul Kim(KAERI) | PDF보기 | - |
| 2021-Spring | 4B : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.13(Thu) 15:35 | On-line | Radiation Shielding Strategy for Material Testing of PWR Reactor Internal Components | Seong Sik Hwang, Sung Hwan Cho, Hyung Ha Jin, Kwon Jae Choi, Sung Woo Kim, and Dong Jin Kim(KAERI) | PDF보기 | PPT보기 |
| 2021-Spring | 4C : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.14(Fri) 09:00 | On-line | IG Cracking of SA508 by Thermal Treatment at 350-420oC | SungSoo Kim and Jong Yup Jeong(KAERI), Young Suk Kim(MACTEC) | PDF보기 | - |
| 2021-Spring | 4C : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.14(Fri) 09:25 | On-line | Corrosion Behavior of Borated Stainless Steel in High DO Boric Acid Water | Daehyeon Park, Yunju Lee, Junhyuk Ham, Seung Chang Yoo, and Ji Hyun Kim(UNIST), Kiyoung Kim and Donghee Lee(KHNP) | PDF보기 | - |
| 2021-Spring | 4C : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.14(Fri) 09:50 | On-line | Corrosion Performance of Coating for Venturi Fouling Mitigation at Nuclear Power Plant | Wonjun Choi and Chi Bum Bahn(PNU), Young-Jin Kim, Dong-Seok Lim, and Hyun-Chul Lee(FNC Tech.) | PDF보기 | PPT보기 |
| 2021-Spring | 4C : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.14(Fri) 10:15 | On-line | Improvement of Alkali Silicate Heat-Resistant Coating According to ZIRLO’s Surface Treatment Method | Boyeon Kweon, Gyu Hyeon Shim, Ji Hoon Kim, Dong Ho Nguyen, and Ho Seon Ahn(INU) | PDF보기 | - |
| 2021-Spring | 4C : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.14(Fri) 10:40 | On-line | Post-LOCA Ductility of Cr-coated Cladding and Its Implications on Accident Coping Time | Hyunwoo Yook, Kyunghwan Keum, Dongju Kim, and Youho Lee(SNU) | PDF보기 | PPT보기 |
| 2021-Spring | 4C : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.14(Fri) 11:05 | On-line | Study on Fe-Cr-Al Alloys Corrosion on 360 ℃ Simulated Pressurized Water Chemistry Condition | Taeyong Kim, Seung Chang Yoo, Junhyuk Ham, Yunju Lee, In Young Song, and Ji Hyun Kim(UNIST), Sungyu Kim and Chi Bum Bahn(PNU) | PDF보기 | - |
| 2021-Spring | 4C : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 5.14(Fri) 11:30 | On-line | Air Oxidation Behaviors and Kinetics of UO2 and Zircaloy-4 Cladding under Spent Fuel Pool Accident Condition | Sun-Ki Kim(KAERI) | PDF보기 | - |
Last Modified : 1998-Autumn
