NUE_Theses_Ph.D.

Issue DateTitleAuthor(s)TypeView
2021-02Study on Electrolysis-based Tritium in Water Real-Time Continuous Monitoring SystemKim, Hee Reyoung; Bae, Jun WooDoctoral thesis45
2021-02Dynamic Radiation Safety Assessment of Workers During the Decommissioning of Radioactive ConcreteKim, Hee Reyoung; Lee, ChoongWieDoctoral thesis30
2020-08Development of integrated nuclear electromagnetic pump for liquid metal cooled micro reactorKim, Hee Reyoung; Kwak, JaesikDoctoral thesis131
2020-08Study on natural circulation of the reactor pool under RVACS operation using fluid to fluid model simulating experimentBang, In Cheol; Lee, Min HoDoctoral thesis121
2020-02Establishment and Application of Diamond Detector Analysis SystemLee, Deokjung; Kong, ChidongDoctoral thesis189
2020-02Gd and B Based Integral Neutron Absorber for Spent Fuel Transportation and Storage SystemLee, Deokjung; Kim, Mi JinDoctoral thesis209
2020-02Optimization of Monitoring System using Plastic Scintillator for Beta nuclide including Tritium in WaterKim, Hee Reyoung; Lee, UkJaeDoctoral thesis241
2019-08A Study on Primary Water Stress Corrosion Cracking Behavior of Forged Alloy 600 in Nuclear Power PlantKim, Ji Hyun; Yoo, Seung ChangDoctoral thesis384
2019-02Phenomenological Study of Fuel Relocation Behavior and Formation of Debris Bed in Metal-fueled Sodium-cooled Fast ReactorBang, In Cheol; Heo, HyoDoctoral thesis489
2019-02Investigation of ZrN Non-Reactively Sputtered Diffusion Barrier Coating for U-Mo Dispersion FuelLee, Deokjung; Kim, Ji HyeonDoctoral thesis330
2019-02Design and modeling of the hydraulic control rod drive mechanism for passive in-core cooling systemBang, In Cheol; Kim, In GukDoctoral thesis349
2019-02Development of relocation model of molten metallic fuel in core disruptive accident of sodium-cooled fast reactorBang, In Cheol; Moon, SungboDoctoral thesis272
2019-02Development of a New Monte Carlo Code for High-Fidelity Power Reactor AnalysisLee, Deokjung; Lee, HyunsukDoctoral thesis383
2019-02Study on the Multiphysics Modeling of Molten Salt Reactor Using Adjoint-based Sensitivity Analysis MethodBang, In Cheol; Jeong, Yeong ShinDoctoral thesis431
2019-02Novel Technologies for Mitigation of Flow Accelerated Corrosion of the Secondary Side of Pressurized Water ReactorsKim, Ji Hyun; Kim, SeunghyunDoctoral thesis344
2019-02Modeling of Radiation-induced Dimensional Instability of Metals and Alloys in Nuclear Systems: Improved Understanding of the Stress and Alloying Elements Effects by Rate TheoryKim, Ji Hyun; Choi, Sang IlDoctoral thesis304
2018-08A Study on Pre-Transition Corrosion Behavior of Zirconium Alloy in Simulated Primary Water Conditions of Nuclear Power PlantKim, Ji Hyun; Kim, TaehoDoctoral thesis365
2018-08Measurements and Modeling of Thermal Conductivity of U-Mo/Al Dispersion Fuel for Research ReactorLee, Deokjung; Cho, Tae WonDoctoral thesis393
2018-08Enhanced Accident Performance of Zirconium Alloy Cladding Tube by High-Temperature Preformed Oxide and Analysis of Preformed Oxide MicrostructuresLee, Deokjung; Lee, Cheol MinDoctoral thesis376
2018-08Study on Heat Transfer behavior of High-Prandtl number fluid and its feasibility to Passive Heat Transport SystemBang, In Cheol; Seo, Seok BinDoctoral thesis364

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