Issue DateTitleAuthor(s)TypeView
2020-08Development of integrated nuclear electromagnetic pump for liquid metal cooled micro reactorKim, Hee Reyoung; Kwak, JaesikDoctoral thesis6
2020-08Study on natural circulation of the reactor pool under RVACS operation using fluid to fluid model simulating experimentBang, In Cheol; Lee, Min HoDoctoral thesis15
2020-02Establishment and Application of Diamond Detector Analysis SystemLee, Deokjung; Kong, ChidongDoctoral thesis79
2020-02Gd and B Based Integral Neutron Absorber for Spent Fuel Transportation and Storage SystemLee, Deokjung; Kim, Mi JinDoctoral thesis84
2020-02Optimization of Monitoring System using Plastic Scintillator for Beta nuclide including Tritium in WaterKim, Hee Reyoung; Lee, UkJaeDoctoral thesis106
2019-08A Study on Primary Water Stress Corrosion Cracking Behavior of Forged Alloy 600 in Nuclear Power PlantKim, Ji Hyun; Yoo, Seung ChangDoctoral thesis230
2019-02Phenomenological Study of Fuel Relocation Behavior and Formation of Debris Bed in Metal-fueled Sodium-cooled Fast ReactorBang, In Cheol; Heo, HyoDoctoral thesis333
2019-02Investigation of ZrN Non-Reactively Sputtered Diffusion Barrier Coating for U-Mo Dispersion FuelLee, Deokjung; Kim, Ji HyeonDoctoral thesis215
2019-02Design and modeling of the hydraulic control rod drive mechanism for passive in-core cooling systemBang, In Cheol; Kim, In GukDoctoral thesis213
2019-02Development of relocation model of molten metallic fuel in core disruptive accident of sodium-cooled fast reactorBang, In Cheol; Moon, SungboDoctoral thesis167
2019-02Development of a New Monte Carlo Code for High-Fidelity Power Reactor AnalysisLee, Deokjung; Lee, HyunsukDoctoral thesis251
2019-02Study on the Multiphysics Modeling of Molten Salt Reactor Using Adjoint-based Sensitivity Analysis MethodBang, In Cheol; Jeong, Yeong ShinDoctoral thesis294
2019-02Novel Technologies for Mitigation of Flow Accelerated Corrosion of the Secondary Side of Pressurized Water ReactorsKim, Ji Hyun; Kim, SeunghyunDoctoral thesis226
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 thesis191
2018-08A Study on Pre-Transition Corrosion Behavior of Zirconium Alloy in Simulated Primary Water Conditions of Nuclear Power PlantKim, Ji Hyun; Kim, TaehoDoctoral thesis249
2018-08Measurements and Modeling of Thermal Conductivity of U-Mo/Al Dispersion Fuel for Research ReactorLee, Deokjung; Cho, Tae WonDoctoral thesis280
2018-08Enhanced Accident Performance of Zirconium Alloy Cladding Tube by High-Temperature Preformed Oxide and Analysis of Preformed Oxide MicrostructuresLee, Deokjung; Lee, Cheol MinDoctoral thesis245
2018-08Study on Heat Transfer behavior of High-Prandtl number fluid and its feasibility to Passive Heat Transport SystemBang, In Cheol; Seo, Seok BinDoctoral thesis249
2018-02Irradiation Performance Modeling and PRIME Code Development for U-Mo Dispersion Fuel for Research ReactorsSohn, Dong-Seong; Jeong, Gwan YoonDoctoral thesis330
2017-08Thermal Aging Effects on Fusion Boundary of Dissimilar Metal Weldments in Primary Coolant System of Nuclear Power PlantKim, Ji Hyun; Choi, Kyoung JoonDoctoral thesis445