| 2021-02 | Study on Electrolysis-based Tritium in Water Real-Time Continuous Monitoring System | Kim, Hee Reyoung; Bae, Jun Woo | Doctoral thesis | 14 |
| 2021-02 | Dynamic Radiation Safety Assessment of Workers During the Decommissioning of Radioactive Concrete | Kim, Hee Reyoung; Lee, ChoongWie | Doctoral thesis | 11 |
| 2020-08 | Development of integrated nuclear electromagnetic pump for liquid metal cooled micro reactor | Kim, Hee Reyoung; Kwak, Jaesik | Doctoral thesis | 97 |
| 2020-08 | Study on natural circulation of the reactor pool under RVACS operation using fluid to fluid model simulating experiment | Bang, In Cheol; Lee, Min Ho | Doctoral thesis | 87 |
| 2020-02 | Establishment and Application of Diamond Detector Analysis System | Lee, Deokjung; Kong, Chidong | Doctoral thesis | 147 |
| 2020-02 | Gd and B Based Integral Neutron Absorber for Spent Fuel Transportation and Storage System | Lee, Deokjung; Kim, Mi Jin | Doctoral thesis | 166 |
| 2020-02 | Optimization of Monitoring System using Plastic Scintillator for Beta nuclide including Tritium in Water | Kim, Hee Reyoung; Lee, UkJae | Doctoral thesis | 204 |
| 2019-08 | A Study on Primary Water Stress Corrosion Cracking Behavior of Forged Alloy 600 in Nuclear Power Plant | Kim, Ji Hyun; Yoo, Seung Chang | Doctoral thesis | 345 |
| 2019-02 | Phenomenological Study of Fuel Relocation Behavior and Formation of Debris Bed in Metal-fueled Sodium-cooled Fast Reactor | Bang, In Cheol; Heo, Hyo | Doctoral thesis | 450 |
| 2019-02 | Investigation of ZrN Non-Reactively Sputtered Diffusion Barrier Coating for U-Mo Dispersion Fuel | Lee, Deokjung; Kim, Ji Hyeon | Doctoral thesis | 297 |
| 2019-02 | Design and modeling of the hydraulic control rod drive mechanism for passive in-core cooling system | Bang, In Cheol; Kim, In Guk | Doctoral thesis | 310 |
| 2019-02 | Development of relocation model of molten metallic fuel in core disruptive accident of sodium-cooled fast reactor | Bang, In Cheol; Moon, Sungbo | Doctoral thesis | 235 |
| 2019-02 | Development of a New Monte Carlo Code for High-Fidelity Power Reactor Analysis | Lee, Deokjung; Lee, Hyunsuk | Doctoral thesis | 349 |
| 2019-02 | Study on the Multiphysics Modeling of Molten Salt Reactor Using Adjoint-based Sensitivity Analysis Method | Bang, In Cheol; Jeong, Yeong Shin | Doctoral thesis | 384 |
| 2019-02 | Novel Technologies for Mitigation of Flow Accelerated Corrosion of the Secondary Side of Pressurized Water Reactors | Kim, Ji Hyun; Kim, Seunghyun | Doctoral thesis | 310 |
| 2019-02 | Modeling of Radiation-induced Dimensional Instability of Metals and Alloys in Nuclear Systems: Improved Understanding of the Stress and Alloying Elements Effects by Rate Theory | Kim, Ji Hyun; Choi, Sang Il | Doctoral thesis | 266 |
| 2018-08 | A Study on Pre-Transition Corrosion Behavior of Zirconium Alloy in Simulated Primary Water Conditions of Nuclear Power Plant | Kim, Ji Hyun; Kim, Taeho | Doctoral thesis | 329 |
| 2018-08 | Measurements and Modeling of Thermal Conductivity of U-Mo/Al Dispersion Fuel for Research Reactor | Lee, Deokjung; Cho, Tae Won | Doctoral thesis | 357 |
| 2018-08 | Enhanced Accident Performance of Zirconium Alloy Cladding Tube by High-Temperature Preformed Oxide and Analysis of Preformed Oxide Microstructures | Lee, Deokjung; Lee, Cheol Min | Doctoral thesis | 331 |
| 2018-08 | Study on Heat Transfer behavior of High-Prandtl number fluid and its feasibility to Passive Heat Transport System | Bang, In Cheol; Seo, Seok Bin | Doctoral thesis | 317 |
