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

Thesis Issue Date2019-02 View6

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

Thesis Issue Date2019-02 View8

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

Thesis Issue Date2019-02 View5

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

Jeong, Yeong Shin

Thesis Issue Date2019-02 View4

A Study on Pre-Transition Corrosion Behavior of Zirconium Alloy in Simulated Primary Water Conditions of Nuclear Power Plant File

Thesis Issue Date2018-08 View4

Safety Assessment Framework of Bioshield Decommissioning Worker File

Thesis Issue Date2018-08 View6

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

Thesis Issue Date2018-08 View7

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

Thesis Issue Date2018-08 View6

Enhanced Accident Performance of Zirconium Alloy Cladding Tube by High-Temperature Preformed Oxide and Analysis of Preformed Oxide Microstructures 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 View5

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

Jeong, Sanggeol

Thesis Issue Date2018-08 View1

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

Thesis Issue Date2018-08 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 View9

Irradiation Performance Modeling and PRIME Code Development for U-Mo Dispersion Fuel for Research Reactors File

Jeong, Gwan Yoon

Thesis Issue Date2018-02 View5

ON-SITE LASER-INDUCED BREAKDOWN SPECTROSCOPY (LIBS) FOR POSTDETONATION NUCLEAR FORENSICS IN REAL TIME File

Thesis Issue Date2018-02 View5

Radiological Impact Assessment of the Korean Peninsula due to Foreign Nuclear Accident File

Thesis Issue Date2018-02 View6

Design and Performance of Hybrid Control Rod For Passive IN-core Cooling System File

Thesis Issue Date2017-08 View6

Effect of Gd-alloyed Neutron Absorber on Thermal Performance of a Spent Fuel Cask File

Thesis Issue Date2017-08 View4

Thermal Aging Effects on Fusion Boundary of Dissimilar Metal Weldments in Primary Coolant System of Nuclear Power Plant File

Thesis Issue Date2017-08 View5

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