Issue DateTitleAuthor(s)TypeView
2023-08Study on Degradation of Polymer under Normal Operation and Accident Environment of Nuclear Power PlantsKim, Ji Hyun; Song, InyoungDoctoral thesis28
2023-08Development of Nodal Diffusion Code for VVER and HTGR analysis with Advanced Semi Analytic Nodal MethodLee, Deokjung; Jang, JaerimDoctoral thesis38
2023-08Development of a Nodal Diffusion Code for Fast Reactor Analysis and DesignLee, Deokjung; Tran, Tuan QuocDoctoral thesis56
2023-08Focusing Grade as a Measure for Graded Approaches to Safety Culture Management in the Nuclear IndustryLee, Seung Jun; Ahn, JeeyeaDoctoral thesis28
2023-08Automated Startup Operation for Nuclear Power Plants based on Multi-Agents with Plant Parameter Prediction ModelLee, Seung Jun; Kim, Jae MinDoctoral thesis36
2023-08Development of Reactor Multiphysics framework to analyze the effect of crossflow and dynamic gHTC for Depletion and REA transientLee, Deokjung; Zahur, AwaisDoctoral thesis36
2023-02A Comparison Study of the Predictor-Corrector Quasi-static Method and CMFD-based Transient Fixed Source Problem for Transient AnalysisLee, Deokjung; Rahman, AnisurDoctoral thesis631
2023-02A Safety Analysis Code for Al-B4C Neutron Absorbers Used in Spent Nuclear Fuel PoolAhn, Sangjoon; Kim, GeonDoctoral thesis532
2023-02Thermophysical property and material compatibility of accident-tolerant UO2-U3Si2 composite fuelAhn, Sangjoon; Ahn, JungsuDoctoral thesis556
2023-02Development of Zirconium Decontamination Process by Combining Molten Salt Electrolysis and Pyrolysis of Irradiated Zr-alloy WastePark, Jaeyeong; Hur, JunghoDoctoral thesis542
2023-02A Study on Directed Energy Deposition Process of Corrosion Resistant Coating for Lead-Bismuth Eutectic EnvironmentKim, Ji Hyun; Kim, GidongDoctoral thesis622
2023-02Monte Carlo Code MCS as Cross-section Generation Tool for Reactor Core AnalysisLee, Deokjung; NGUYEN, TUNG DONG CAODoctoral thesis499
2022-08Simulation Optimization Framework for Dynamic Probabilistic Safety Assessment of Nuclear Power PlantsLee, Seung Jun; Park, Jong WooDoctoral thesis821
2022-02In Situ YAlO3(Ce) Gamma Spectrometry System for Underwater Survey by Remotely Operated VehicleKim, Hee Reyoung; Lee, ChankiDoctoral thesis971
2022-02Development of a Spent Nuclear Fuel Radiation Source Term FrameworkLee, Deokjung; Ebiwonjumi, BamideleDoctoral thesis1141
2021-08Development of Chloride Induced Stress Corrosion Cracking Resistant Alloys for Spent Nuclear Fuel Dry Storage CanistersKim, Ji Hyun; Lee, JeonghyeonDoctoral thesis1076
2021-08Computational Study of Stress Corrosion Cracking on Nickel Based Alloy Exposed to Water EnvironmentKim, Ji Hyun; Ko, KwangBeomDoctoral thesis1113
2021-08Gadolinium added uranium mononitride fuels for light water reactor applications: fabrication and thermophysical property measurementsAhn, Sangjoon; Kim, GyeonghunDoctoral thesis1169
2021-08The Angle-dependent Linear Source Approximation for the Three-Dimensional Method of Characteristics/Diamond-Differencing Neutron Transport SimulationLee, Deokjung; Choe, JiwonDoctoral thesis1391