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Establishment and Application of Diamond Detector Analysis System File

Thesis Issue Date2020-02 View7

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 View7

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

Thesis Issue Date2019-02 View8

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

Thesis Issue Date2019-02 View7

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

Thesis Issue Date2019-02 View9

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

Thesis Issue Date2019-02 View22

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

Thesis Issue Date2019-02 View4

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

Thesis Issue Date2019-02 View8

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

Thesis Issue Date2019-02 View5

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

Jeong, Yeong Shin

Thesis Issue Date2019-02 View5

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

Thesis Issue Date2018-08 View8

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

Thesis Issue Date2018-08 View7

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 View8

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

Jeong, Gwan Yoon

Thesis Issue Date2018-02 View9

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

Choi, Kyoung Joon

Thesis Issue Date2017-08 View7

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

Thesis Issue Date2017-08 View7

Development of Ultra-long Cycle Small Modular Sodium-cooled Fast Reactor Core Concept File File

Thesis Issue Date2017-02 View8

Pin-based Pointwise Energy Slowing-down Method for Resonance Self-shielding Calculation File File

Thesis Issue Date2017-02 View9

Effects of Surface Characteristics in Pool Boiling Critical Heat Flux Enhancement, and its Prediction Model File File

Thesis Issue Date2017-02 View8

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