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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 View11
3D-printed heat pipe with advanced capillary wick structure for large-scale nuclear power plant applications File

Park, Ye Yeong

Thesis Issue Date2024-02 View18
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 View18
A Safety Analysis Code for Al-B4C Neutron Absorbers Used in Spent Nuclear Fuel Pool File File

Kim, Geon

Thesis Issue Date2023-02 View18
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 View18
A Study on Directed Energy Deposition Process of Corrosion Resistant Coating for Lead-Bismuth Eutectic Environment File File

Kim, Gidong

Thesis Issue Date2023-02 View15
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 View15
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 View14
Automated Startup Operation for Nuclear Power Plants based on Multi-Agents with Plant Parameter Prediction Model File

Kim, Jae Min

Thesis Issue Date2023-08 View15
Computational Study of Stress Corrosion Cracking on Nickel Based Alloy Exposed to Water Environment File File

Ko, KwangBeom

Thesis Issue Date2021-08 View29
Corrosion protection of Ni-based alloys in molten chloride salt via nickel coating File

Jeon, Younghwan

Thesis Issue Date2024-02 View10
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 View12
Design and Performance of Hybrid Control Rod For Passive IN-core Cooling System File File

Kim, Kyung Mo

Thesis Issue Date2017-08 View18
Development of a New Monte Carlo Code for High-Fidelity Power Reactor Analysis File File

Lee, Hyunsuk

Thesis Issue Date2019-02 View14
Development of a Nodal Diffusion Code for Fast Reactor Analysis and Design File

Tran, Tuan Quoc

Thesis Issue Date2023-08 View15
Development of a Spent Nuclear Fuel Radiation Source Term Framework File File

Bamidele Ebiwonjumi

Thesis Issue Date2022-02 View5
Development of alumina forming Ti-modified austenitic stainless steel for nuclear fuel cladding in lead-bismuth cooled fast reactors File

Kim, Taeyong

Thesis Issue Date2024-02 View14
Development of an AI-driven system for predicting and diagnosing axial offset anomaly during nuclear reactor core operation File

Kim, Hanjoo

Thesis Issue Date2024-02 View17
Development of Chloride Induced Stress Corrosion Cracking Resistant Alloys for Spent Nuclear Fuel Dry Storage Canisters File File

Lee, Jeonghyeon

Thesis Issue Date2021-08 View9
Development of Integrated Nuclear Electromagnetic Pump for Liquid Metal Cooled Micro Reactor File File

Kwak, Jaesik

Thesis Issue Date2020-08 View13
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