학술발표회 논문집
| Year | Div | Date/Time | ROOM | Title | Author | Abstract File | Presentation File |
|---|---|---|---|---|---|---|---|
| 2019-Spring | 5H : 원자력 열수력 (Nuclear Thermal Hydraulics) | 5.23(Thu) 13:00 | 로비 (3F) | Preliminary Study of the Artificial Neural Networks to Replace the Constitutive Equations in the Reactor Safety Analysis Code | ChoHwan Oh, Sung Gil Shin, Seongmin Son, Doh Hyeon Kim, and Jeong Ik Lee(KAIST) | PDF보기 | - |
| 2019-Spring | 5H : 원자력 열수력 (Nuclear Thermal Hydraulics) | 5.23(Thu) 13:00 | 로비 (3F) | Preliminary Calculation of SGTR with HPSI Failure in OPR1000 using SPACE Code | Dong-ha Lee, Yeon-sik Cho, and Jae-seung Suh(SENTECH) | PDF보기 | - |
| 2019-Spring | 5H : 원자력 열수력 (Nuclear Thermal Hydraulics) | 5.23(Thu) 13:00 | 로비 (3F) | Sensitivity Analysis of Reflood Model with RBHT Experiment | Wonwoong Lee and Jeong Ik Lee(KAIST) | PDF보기 | - |
| 2019-Spring | 5H : 원자력 열수력 (Nuclear Thermal Hydraulics) | 5.23(Thu) 13:00 | 로비 (3F) | Preliminary Study on Modified Steam Turbine Modeling of the MARS-KS Code | Doh Hyeon Kim, Jae Jun Lee, Jeong Yeol Baek, Yonghee Kim, and Jeong Ik Lee(KAIST) | PDF보기 | - |
| 2019-Spring | 5H : 원자력 열수력 (Nuclear Thermal Hydraulics) | 5.23(Thu) 13:00 | 로비 (3F) | Thermal-Hydraulic Analysis of MSGTR Event in OPR1000 using SPACE Code | Jae-ho Bae, Yeon-sik Cho, and Jae-seung Suh(SENTECH) | PDF보기 | - |
| 2019-Spring | 5H : 원자력 열수력 (Nuclear Thermal Hydraulics) | 5.23(Thu) 13:00 | 로비 (3F) | Preliminary Study of Correlation between Variables in Sensitivity Analysis of PWR Safety Analysis | Min-Gil Kim and Jeong Ik Lee(KAIST) | PDF보기 | - |
| 2019-Spring | 5H : 원자력 열수력 (Nuclear Thermal Hydraulics) | 5.23(Thu) 13:00 | 로비 (3F) | Preliminary Multi-Physics Analysis of OPR1000 Reactor Core using Coupled CUPID and nTER | Youyeon Choi and Hyoung Kyu Cho(SNU), Jin Young Cho(KAERI) | PDF보기 | - |
| 2019-Spring | 5H : 원자력 열수력 (Nuclear Thermal Hydraulics) | 5.23(Thu) 13:00 | 로비 (3F) | Design Study of Heat Pipes for Nuclear Spaceship Applications | Ye Yeong Park, YeongShin Jeong, and In Cheol Bang(UNIST) | PDF보기 | - |
| 2019-Spring | 5H : 원자력 열수력 (Nuclear Thermal Hydraulics) | 5.23(Thu) 13:00 | 로비 (3F) | Flow Characteristics of Molten Salt Natural Circulation in Non-uniform Heat Flux Condition using Open FOAM | Dong Hun Lee, Seok Bin Seo, Yeong Shin Jeong, and In Cheol Bang(UNIST) | PDF보기 | - |
| 2019-Spring | 5H : 원자력 열수력 (Nuclear Thermal Hydraulics) | 5.23(Thu) 13:00 | 로비 (3F) | Thermal Hydraulic Analysis of TES Integrated PWR Cycle | Ju Yeon Lee and Jeong Ik Lee(KAIST) | PDF보기 | - |
| 2019-Spring | 6A : 원자력 안전 (Nuclear Safety) | 5.23(Thu) 09:00 | 202B (2F) | Simulator-based Time Reliability Curve for HRA of Digitalized Main Control Room | Wondea Jung(KAERI), Eun-chan Lee(KHNP CRI) | PDF보기 | - |
| 2019-Spring | 6A : 원자력 안전 (Nuclear Safety) | 5.23(Thu) 09:20 | 202B (2F) | Application of a PSA Tool for Accident Sequence Precursor Evaluation | Chang-Ju Lee and Dongju Jang(KINS), Sang Hoon Han(KAERI) | PDF보기 | - |
| 2019-Spring | 6A : 원자력 안전 (Nuclear Safety) | 5.23(Thu) 09:40 | 202B (2F) | A Preliminary Site Risk Assessment for Multi-unit Nuclear Power Plants | Wonjong Song, Seunghyun Jang, Dohyun Lim, Yein Seo, Sunghyun Park, and Moosung Jae(HYU) | PDF보기 | - |
| 2019-Spring | 6A : 원자력 안전 (Nuclear Safety) | 5.23(Thu) 10:00 | 202B (2F) | External Flood Risk Analysis at NPP Site Considering Climate Change | Beomjin Kim and Kun-yeun Han(KNU), Daegi Hahm, minkyu Kim, and Junhee Park(KAERI) | PDF보기 | - |
| 2019-Spring | 6A : 원자력 안전 (Nuclear Safety) | 5.23(Thu) 10:20 | 202B (2F) | Development of Software to Estimate Representative Surface Roughness Length in Korea | Sung-yeop Kim, Seung-Cheol Jang, and Kwang-Il Ahn(KAERI), Seok-Won Hwang(KHNP CRI) | PDF보기 | - |
Last Modified : 1998-Autumn
