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10B(n, α)7Li Reaction Accelerated Degradation of Al-B4C Neutron Absorber Used in Spent Nuclear Fuel Pool File File

Jung, Yunsong

Thesis Issue Date2021-08 View96

3D-printed heat pipe with advanced capillary wick structure for large-scale nuclear power plant applications File

Park, Ye Yeong

Thesis Issue Date2024-02 View97

A Comparison Study of the Predictor-Corrector Quasi-static Method and CMFD-based Transient Fixed Source Problem for Transient Analysis File File

Rahman, Anisur

Thesis Issue Date2023-02 View99

A Safety Analysis Code for Al-B4C Neutron Absorbers Used in Spent Nuclear Fuel Pool File File

Kim, Geon

Thesis Issue Date2023-02 View95

A Study in Corrosion Behaviors of Ferritic/Martensitic Steels in Liquid Sodium Condition for Sodium-cooled Fast Reactor Application File File

Shin, Sang Hun

Thesis Issue Date2015-02 View123

A Study on Directed Energy Deposition Process of Corrosion Resistant Coating for Lead-Bismuth Eutectic Environment File File

Kim, Gidong

Thesis Issue Date2023-02 View86

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

Kim, Taeho

Thesis Issue Date2018-08 View83

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

ADVANCED CAD-TO-SIMULATION INTERFACE FOR UNSTRUCTURED MESH SIMULATIONS IN VERSATILE FUSION DEVICES File

Moon, Taeuk

Thesis Issue Date2026-02 View20

Analysis of Thermal Aging Characteristics of Epoxy-Based Neutron Shielding Materials for Dry Storage Applications File

Kang, Tae Uk

Thesis Issue Date2025-08 View36

Assessment of Disposal of Mixed Radioactive Waste Containing Heavy Metals in Low-and Intermediate- Level Waste Disposal Facilities File

Lee, Yulim

Thesis Issue Date2025-08 View54

Automated Startup Operation for Nuclear Power Plants based on Multi-Agents with Plant Parameter Prediction Model File

Kim, Jae Min

Thesis Issue Date2023-08 View90

Axial Function Based on an Asymmetric 4-Point Finite Difference Method for 3D MOC/DD Neutron Transport Calculations File

Lee, Woonghee

Thesis Issue Date2025-08 View226

Computational Study of Stress Corrosion Cracking on Nickel Based Alloy Exposed to Water Environment File File

Ko, KwangBeom

Thesis Issue Date2021-08 View97

Corrosion protection of Ni-based alloys in molten chloride salt via nickel coating File

Jeon, Younghwan

Thesis Issue Date2024-02 View87

Deep Learning-based Optimized Simulation and Consequence Estimation with Neural Network Uncertainty for Dynamic Risk Assessment of Nuclear Power Plants File

Bae, Junyong

Thesis Issue Date2025-02 View79

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

Kim, In Guk

Thesis Issue Date2019-02 View168

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

Kim, Kyung Mo

Thesis Issue Date2017-08 View132

Development of a GPU-Based Time-Dependent Monte Carlo Code System for High-Fidelity Large- Scale Nuclear Reactor Transient Analysis File File

Jeong, Eun

Thesis Issue Date2024-08 View243

Development of a new GPU-optimized Monte Carlo code for Fresh Fuel Pressurized Water Reactor Analysis and Design File

Muhammad Rizwan Ali

Thesis Issue Date2025-02 View89

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