2023-08 | Study on Degradation of Polymer under Normal Operation and Accident Environment of Nuclear Power Plants | Kim, Ji Hyun; Song, Inyoung | Doctoral thesis | 28 |
2023-08 | Development of Nodal Diffusion Code for VVER and HTGR analysis with Advanced Semi Analytic Nodal Method | Lee, Deokjung; Jang, Jaerim | Doctoral thesis | 38 |
2023-08 | Development of a Nodal Diffusion Code for Fast Reactor Analysis and Design | Lee, Deokjung; Tran, Tuan Quoc | Doctoral thesis | 56 |
2023-08 | Focusing Grade as a Measure for Graded Approaches to Safety Culture Management in the Nuclear Industry | Lee, Seung Jun; Ahn, Jeeyea | Doctoral thesis | 28 |
2023-08 | Automated Startup Operation for Nuclear Power Plants based on Multi-Agents with Plant Parameter Prediction Model | Lee, Seung Jun; Kim, Jae Min | Doctoral thesis | 36 |
2023-08 | Development of Reactor Multiphysics framework to analyze the effect of crossflow and dynamic gHTC for Depletion and REA transient | Lee, Deokjung; Zahur, Awais | Doctoral thesis | 36 |
2023-02 | A Comparison Study of the Predictor-Corrector Quasi-static Method and CMFD-based Transient Fixed Source Problem for Transient Analysis | Lee, Deokjung; Rahman, Anisur | Doctoral thesis | 631 |
2023-02 | A Safety Analysis Code for Al-B4C Neutron Absorbers Used in Spent Nuclear Fuel Pool | Ahn, Sangjoon; Kim, Geon | Doctoral thesis | 532 |
2023-02 | Thermophysical property and material compatibility of accident-tolerant UO2-U3Si2 composite fuel | Ahn, Sangjoon; Ahn, Jungsu | Doctoral thesis | 556 |
2023-02 | Development of Zirconium Decontamination Process by Combining Molten Salt Electrolysis and Pyrolysis of Irradiated Zr-alloy Waste | Park, Jaeyeong; Hur, Jungho | Doctoral thesis | 542 |
2023-02 | A Study on Directed Energy Deposition Process of Corrosion Resistant Coating for Lead-Bismuth Eutectic Environment | Kim, Ji Hyun; Kim, Gidong | Doctoral thesis | 622 |
2023-02 | Monte Carlo Code MCS as Cross-section Generation Tool for Reactor Core Analysis | Lee, Deokjung; NGUYEN, TUNG DONG CAO | Doctoral thesis | 499 |
2022-08 | Simulation Optimization Framework for Dynamic Probabilistic Safety Assessment of Nuclear Power Plants | Lee, Seung Jun; Park, Jong Woo | Doctoral thesis | 821 |
2022-02 | In Situ YAlO3(Ce) Gamma Spectrometry System for Underwater Survey by Remotely Operated Vehicle | Kim, Hee Reyoung; Lee, Chanki | Doctoral thesis | 971 |
2022-02 | Development of a Spent Nuclear Fuel Radiation Source Term Framework | Lee, Deokjung; Ebiwonjumi, Bamidele | Doctoral thesis | 1141 |
2021-08 | Development of Chloride Induced Stress Corrosion Cracking Resistant Alloys for Spent Nuclear Fuel Dry Storage Canisters | Kim, Ji Hyun; Lee, Jeonghyeon | Doctoral thesis | 1076 |
2021-08 | MICROSTRUCTURAL INSTABILITY EVOLVED IN ION-IRRADIATED FERRITIC/MARTENSITIC STEELS AT HIGH RADIATION DAMAGE LEVELS | Ahn, Sangjoon; Lee, Myeongkyu | Doctoral thesis | 1200 |
2021-08 | Computational Study of Stress Corrosion Cracking on Nickel Based Alloy Exposed to Water Environment | Kim, Ji Hyun; Ko, KwangBeom | Doctoral thesis | 1113 |
2021-08 | Gadolinium added uranium mononitride fuels for light water reactor applications: fabrication and thermophysical property measurements | Ahn, Sangjoon; Kim, Gyeonghun | Doctoral thesis | 1169 |
2021-08 | The Angle-dependent Linear Source Approximation for the Three-Dimensional Method of Characteristics/Diamond-Differencing Neutron Transport Simulation | Lee, Deokjung; Choe, Jiwon | Doctoral thesis | 1391 |