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Abnormality Diagnosis System for Nuclear Power Plants Using Multiple Gated Recurrent Unit Algorithms File

Thesis Issue Date2019-08 View6

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

Jeong, Yeong Shin

Thesis Issue Date2019-02 View4

QUANTITATIVE SOFTWARE RELIABILITY ASSESSMENT OF THE SAFETY CRITICAL IN NUCLEAR REACTOR PROTECTION SYSTEM File

Thesis Issue Date2019-02 View5

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

Thesis Issue Date2019-02 View3

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

Thesis Issue Date2019-02 View5

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 File

Thesis Issue Date2019-02 View4

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

Thesis Issue Date2019-02 View4

EXPERIMENTAL STUDY OF CORROSION ON STRUCTURAL MATERIALS FOR PYROCHEMICAL PROCESS IN HIGH TEMPERATURE MOLTEN SALTS CONTAINING FISSION PRODUCTS File

Jeong, Hyeonjun

Thesis Issue Date2019-02 View3

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

Thesis Issue Date2019-02 View5

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

Thesis Issue Date2019-02 View4

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

Thesis Issue Date2019-02 View5

Worker Exposure Dose Evaluation of the Steam Generator Decommissioning Process in the Kori-1 File

Thesis Issue Date2018-08 View5

Verification and Validation for Transient Calculation of STREAM/RAST-K 2.0 File

Thesis Issue Date2018-08 View8

Study on Heat Transfer behavior of High-Prandtl number fluid and its feasibility to Passive Heat Transport System File

Thesis Issue Date2018-08 View7

Safety Assessment Framework of Bioshield Decommissioning Worker File

Thesis Issue Date2018-08 View6

MULTI-SPECIES MULTI-PHYSICS MODELING AND VALIDATION OF HYDRODYNAMIC ELECTROCHEMICAL SYSTEM FOR USED NUCLEAR FUEL File

Thesis Issue Date2018-08 View5

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

Thesis Issue Date2018-08 View5

Generation of Windowed Multipole Library for on-the-fly Doppler Broadening in UNIST In-house Monte Carlo Code File

Khassenov, Azamat

Thesis Issue Date2018-08 View4

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

Thesis Issue Date2018-08 View4

Design of High Density Spent Fuel Storage Rack Applying Burnup Credit File

Jeong, Sanggeol

Thesis Issue Date2018-08 View1

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