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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
Development of Nodal Diffusion Code for VVER and HTGR analysis with Advanced Semi Analytic Nodal Method File File

Jang, Jaerim

Thesis Issue Date2023-08 View15
Development of Reactor Multiphysics framework to analyze the effect of crossflow and dynamic gHTC for Depletion and REA transient File File

Awais Zahur

Thesis Issue Date2023-08 View16
Development of relocation model of molten metallic fuel in core disruptive accident of sodium-cooled fast reactor File File

Moon, Sungbo

Thesis Issue Date2019-02 View8
Development of Ultra-long Cycle Small Modular Sodium-cooled Fast Reactor Core Concept File File

Tak, Taewoo

Thesis Issue Date2017-02 View16
Development of Zirconium Decontamination Process by Combining Molten Salt Electrolysis and Pyrolysis of Irradiated Zr-alloy Waste File File

Hur, Jungho

Thesis Issue Date2023-02 View17
Dry-out limit enhancement and optimal filling ratio determination in sodium heat pipes based on the overfilling effect File

Lee, Dong Hun

Thesis Issue Date2024-02 View23
Dynamic Radiation Safety Assessment of Workers During the Decommissioning of Radioactive Concrete File File

Lee, ChoongWieLee

Thesis Issue Date2021-02 View8
Effect of CRUD deposition on the sub-cooled nucleate boiling characteristics of fuel cladding in pressurized water reactor operating condition File

Kim, Ji Yong

Thesis Issue Date2024-02 View17
Effects of Graphene and SiC Nanofluids on Critical Heat Flux and Quenching for Advanced Nuclear Reactors File File

Lee, Seung Won

Thesis Issue Date2013-11 View21
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