학술발표회 논문집
Year | Div | Date/Time | ROOM | Title | Author | Abstract File | Presentation File |
---|---|---|---|---|---|---|---|
2023-Spring | 10F : 원전건설 및 운영기술 (Nuclear Power Plant Construction and Operation Technology) | 5.18(Thu) 09:00 | 402A (4F) | Cyclic Lateral Loading Test of Cylindrical Wall for Seismic Evaluation of Containment Building | Hyeon Keun Yang(KAERI), Hong Gun Park(SNU) | PDF보기 | - |
2023-Spring | 10F : 원전건설 및 운영기술 (Nuclear Power Plant Construction and Operation Technology) | 5.18(Thu) 09:20 | 402A (4F) | Rules of Structural Integrity Evaluation for Class-A Components of High Temperature Reactors | Gyeong-Hoi Koo, Na-Hyun Kim, Si-Hwa Jeong, and Sang-Ji Kim(KAERI) | PDF보기 | - |
2023-Spring | 10F : 원전건설 및 운영기술 (Nuclear Power Plant Construction and Operation Technology) | 5.18(Thu) 09:40 | 402A (4F) | Review of Failure Mechanism of Tensile Anchors in Concrete | Ilhwan Moon, Chang Beum Park, Sungmin Lee, and Yunho Nam(KEPCO E&C) | PDF보기 | - |
2023-Spring | 10F : 원전건설 및 운영기술 (Nuclear Power Plant Construction and Operation Technology) | 5.18(Thu) 10:00 | 402A (4F) | Evaluating Fluid Leakage through Concrete Crack | Se-Yun Kim, Sung-Wook Hong, Donghwi Eum, and Tong-Seok Han(Yonsei Univ.) | PDF보기 | - |
2023-Spring | 10F : 원전건설 및 운영기술 (Nuclear Power Plant Construction and Operation Technology) | 5.18(Thu) 10:20 | 402A (4F) | Characterization of the Nonlinear Behavior of the piping T-joints by Experiment and Finite Element Analysis | Sung Gook Cho, Gihwan So, and Jee Hoon Moo(Innose Tech.), ABhinav Gupta(North Carolina State Univ.) | PDF보기 | - |
2023-Spring | 10F : 원전건설 및 운영기술 (Nuclear Power Plant Construction and Operation Technology) | 5.18(Thu) 11:00 | 402A (4F) | Preliminary Study on Leakage Rate Estimation of Cracked Concrete Walls | Yousang Lee and Hong-Gun Park(SNU) | PDF보기 | - |
2023-Spring | 10F : 원전건설 및 운영기술 (Nuclear Power Plant Construction and Operation Technology) | 5.18(Thu) 11:20 | 402A (4F) | Numerical Study on the Concrete Microstructure using Image-based Virtual Element Method | HyeongTae Kim and Kyoungsoo Park(Yonsei Univ.) | PDF보기 | PPT보기 |
2023-Spring | 10F : 원전건설 및 운영기술 (Nuclear Power Plant Construction and Operation Technology) | 5.18(Thu) 11:40 | 402A (4F) | Typhoon Hazard Analysis of Kori Site using Logic Tree | Gungyu Kim and Seunghyun Eem(KNU), Shinyoung Kwag(Hanbat National Univ), Young-Sun Choun(CENITS Corp.), | PDF보기 | - |
2023-Spring | 10F : 원전건설 및 운영기술 (Nuclear Power Plant Construction and Operation Technology) | 5.18(Thu) 12:00 | 402A (4F) | A Study on Structural Integrity Evaluation of CANDU Type SRT | youngyoon Lee and hongpyo Lee(KHNP) | PDF보기 | - |
2023-Spring | 10F : 원전건설 및 운영기술 (Nuclear Power Plant Construction and Operation Technology) | 5.18(Thu) 12:20 | 402A (4F) | A Study on Robust Optimal Sensor Placement for Containment Buildings in Nuclear Power Plants | Chanwoo Lee, Youjin Kim, and Hyung-jo Jung(KAIST) | PDF보기 | - |
2023-Spring | 10G : 원전건설 및 운영기술 (Nuclear Power Plant Construction and Operation Technology) | 5.18(Thu) 13:00 | Lobby (3F) | Review on LCA (Life Cycle Assessment) for CO2 Emissions of the SMR (Small Modular Reactor) | Seong Kuk Cho, Jiyun Lee, Keong Tae Hwang, Hongjo Youn, Yongik Jang, Youngwoo Lee, and Hoyung Shin(HEC) | PDF보기 | - |
2023-Spring | 10G : 원전건설 및 운영기술 (Nuclear Power Plant Construction and Operation Technology) | 5.18(Thu) 13:00 | Lobby (3F) | Development of Flowchart based Technical Specification | Bosang Yun(KHNP), Jonghyun Kim(CSU) | PDF보기 | PPT보기 |
2023-Spring | 10G : 원전건설 및 운영기술 (Nuclear Power Plant Construction and Operation Technology) | 5.18(Thu) 13:00 | Lobby (3F) | A Study on Harmonic Distortion Measurement in NPP | Sungbaek Park and HoonKeun Lee(KINS) | PDF보기 | - |
2023-Spring | 10G : 원전건설 및 운영기술 (Nuclear Power Plant Construction and Operation Technology) | 5.18(Thu) 13:00 | Lobby (3F) | A Study on the Secondary-Primary Coolant Temperature Deviation to Prevent Overpressure During RCP Startup | Jonghoon Kim(KHNP), jonghyun Kim(CSU) | PDF보기 | - |
2023-Spring | 10G : 원전건설 및 운영기술 (Nuclear Power Plant Construction and Operation Technology) | 5.18(Thu) 13:00 | Lobby (3F) | Degradation Mechanisms for Alloy 690 Steam Generator Tubing in Nuclear Power Plants | Chan Hee Cho, Kwan Seob Jang, Ji Eun Jang, and Hee Sung Jung(Sae-An Engineering) | PDF보기 | - |
Last Modified : 1998-Autumn