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Gadolinium added uranium mononitride fuels for light water reactor applications: fabrication and thermophysical property measurements File File

Thesis Issue Date2021-08 View75

The Angle-dependent Linear Source Approximation for the Three-Dimensional Method of Characteristics/Diamond-Differencing Neutron Transport Simulation File File

Thesis Issue Date2021-08 View65

Study on Electrolysis-based Tritium in Water Real-Time Continuous Monitoring System File File

Thesis Issue Date2021-02 View76

Dynamic Radiation Safety Assessment of Workers During the Decommissioning of Radioactive Concrete File File

Lee, ChoongWieLee

Thesis Issue Date2021-02 View104

Study on Natural Circulation of the Reactor Pool under RVACS Operation using Fluid to Fluid Model Simulating Experiment File File

Thesis Issue Date2020-08 View67

Development of Integrated Nuclear Electromagnetic Pump for Liquid Metal Cooled Micro Reactor File File

Thesis Issue Date2020-08 View83

Gd and B Based Integral Neutron Absorber for Spent Fuel Transportation and Storage System File

Thesis Issue Date2020-02 View65

Optimization of Monitoring System using Plastic Scintillator for Beta nuclide including Tritium in Water File

Thesis Issue Date2020-02 View65

Establishment and Application of Diamond Detector Analysis System File

Thesis Issue Date2020-02 View71

A Study on Primary Water Stress Corrosion Cracking Behavior of Forged Alloy 600 in Nuclear Power Plant File File

Yoo, Seung Chang

Thesis Issue Date2019-08 View71

Modeling of Radiation-induced Dimensional Instability of Metals and Alloys in Nuclear Systems File File

Thesis Issue Date2019-02 View51

Investigation of ZrN Non-Reactively Sputtered Diffusion Barrier Coating for U-Mo Dispersion Fuel File File

Thesis Issue Date2019-02 View70

Novel Technologies for Mitigation of Flow Accelerated Corrosion of the Secondary Side of Pressurized Water Reactors File File

Thesis Issue Date2019-02 View62

Phenomenological Study of Fuel Relocation Behavior and Formation of Debris Bed in Metal-fueled Sodium-cooled Fast Reactor File File

Thesis Issue Date2019-02 View90

Study on the Multiphysics Modeling of Molten Salt Reactor Using Adjoint-based Sensitivity Analysis Method File File

Jeong, Yeong Shin

Thesis Issue Date2019-02 View67

Development of a New Monte Carlo Code for High-Fidelity Power Reactor Analysis File File

Thesis Issue Date2019-02 View85

Design and modeling of the hydraulic control rod drive mechanism for passive in-core cooling system File File

Thesis Issue Date2019-02 View168

Development of relocation model of molten metallic fuel in core disruptive accident of sodium-cooled fast reactor File File

Thesis Issue Date2019-02 View55

Enhanced Accident Performance of Zirconium Alloy Cladding Tube by High-Temperature Preformed Oxide and Analysis of Preformed Oxide Microstructures File File

Thesis Issue Date2018-08 View86

Measurements and Modeling of Thermal Conductivity of U-Mo/Al Dispersion Fuel for Research Reactor File File

Thesis Issue Date2018-08 View72

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