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Additional Actinide Separation to Minimize Human Intrusion Radiological Risk of Pyroprocessing Waste File

Thesis Issue Date2021-08 View5

Verification and Validation of Monte Carlo Code MCS for the Multi-physics High-fidelity Analysis of OPR-1000 Multi-cycle Operation File

Thesis Issue Date2020-08 View6

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

Thesis Issue Date2020-08 View5

Sensor fault detection and fault tolerant accident diagnosis system for nuclear power plants File

Thesis Issue Date2020-08 View4

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

Thesis Issue Date2020-08 View5

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

Thesis Issue Date2020-02 View2

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

Thesis Issue Date2020-02 View4

Establishment and Application of Diamond Detector Analysis System File

Thesis Issue Date2020-02 View4

Study on Swirl and Cross Flow of 3D-Printed Rotational Mixing Vane in 2×3 Subchannel File

Thesis Issue Date2019-08 View5

Spatial Distribution of Radioactivity in Bioshield by using Monte Carlo Simulation for Reducing Waste Volume and External Dose during Kori unit 1 Nuclear Power Plant Decommissioning File

Thesis Issue Date2019-08 View3

Neutron XS Library Generation of ENDF/B-VIII.0 for MOC code STREAM and Monte Carlo code MCS File

Thesis Issue Date2019-08 View4

Implementation and Verification of Three-Dimensional MOC Transient Solver in Whole-core Transport code STREAM File

Thesis Issue Date2019-08 View1

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

Yoo, Seung Chang

Thesis Issue Date2019-08 View5

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

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