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

Jeon, Younghwan

Thesis Issue Date2024-02 View2

Investigation of acoustic characteristics in boiling phenomena and deep learning-based boiling monitoring system using acoustic signals File

Thesis Issue Date2024-02 View27

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

Thesis Issue Date2024-02 View1

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

Thesis Issue Date2024-02 View5

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

Thesis Issue Date2024-02 View2

Irradiation enhanced degradation of Al-B4C metal matrix composite neutron absorber in spent nuclear fuel dry storage File

Thesis Issue Date2024-02 View6

Study on continuous monitoring system using integrated beta and gamma detection system for beta and gamma nuclides in water File

Thesis Issue Date2024-02 View2

Quantification and importance analysis with dynamic probabilistic safety assessment

Thesis Issue Date2024-02 View3

Research on identification of multiple beta nuclides measured in the air based on machine learning File

Sung, Si Hyeong

Thesis Issue Date2024-02 View3

Enhancing the energy deposition model in STREAM with photon transport module File

Mai, Nhan Nguyen Trong

Thesis Issue Date2024-02 View10

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

Thesis Issue Date2024-02 View2

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

Thesis Issue Date2024-02 View3

Study on Degradation of Polymer under Normal Operation and Accident Environment of Nuclear Power Plants File

Thesis Issue Date2023-08 View9

Focusing Grade as a Measure for Graded Approaches to Safety Culture Management in the Nuclear Industry File

Thesis Issue Date2023-08 View7

Development of Reactor Multiphysics framework to analyze the effect of crossflow and dynamic gHTC for Depletion and REA transient File

Thesis Issue Date2023-08 View5

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

Thesis Issue Date2023-08 View7

Development of a Nodal Diffusion Code for Fast Reactor Analysis and Design File

Thesis Issue Date2023-08 View8

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

Thesis Issue Date2023-08 View6

Verification and Validation of Whole Core Three-Dimensional MOC Code STREAM3D with Watts Bar Unit 1 Multi-cycle Operation File

AYGUL, MURATSERDAR

Thesis Issue Date2023-02 View8

Thermophysical property and material compatibility of accident-tolerant UO2-U3Si2 composite fuel File

Thesis Issue Date2023-02 View9

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