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Deep Neural Network for Generating Homogenized Fuel Assembly Data for Nodal Codes File

Thesis Issue Date2022-08 View4

Design of High Density Spent Fuel Storage Rack Applying Burnup Credit File

Jeong, Sanggeol

Thesis Issue Date2018-08 View1

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

Thesis Issue Date2019-02 View4

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

Thesis Issue Date2023-08 View7

Development of a Spent Nuclear Fuel Radiation Source Term Framework File

Ebiwonjumi, Bamidele

Thesis Issue Date2022-02 View1

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

Thesis Issue Date2023-08 View6

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

Thesis Issue Date2017-02 View4

Enhanced Accident Performance of Zirconium Alloy Cladding Tube by High-Temperature Preformed Oxide and Analysis of Preformed Oxide Microstructures File

Thesis Issue Date2018-08 View4

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

Mai, Nhan Nguyen Trong

Thesis Issue Date2024-02 View10

Establishment and Application of Diamond Detector Analysis System File

Thesis Issue Date2020-02 View4

Gd and B Based Integral Neutron Absorber for Spent Fuel Transportation and Storage System File

Thesis Issue Date2020-02 View4

Generation of Windowed Multipole Library for on-the-fly Doppler Broadening in UNIST In-house Monte Carlo Code File

Khassenov, Azamat

Thesis Issue Date2018-08 View4

Implementation and Verification of Three-Dimensional MOC Transient Solver in Whole-core Transport code STREAM File

Thesis Issue Date2019-08 View1

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

Thesis Issue Date2019-02 View3

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

Thesis Issue Date2018-08 View5

Monte Carlo Code MCS as Cross-section Generation Tool for Reactor Core Analysis File

NGUYEN, Tung Dong Cao

Thesis Issue Date2023-02 View9

Neutron XS Library Generation of ENDF/B-VIII.0 for MOC code STREAM and Monte Carlo code MCS File

Thesis Issue Date2019-08 View4

New Burnable Absorber and Zirconium Reflector for Advanced PWRs File

Thesis Issue Date2015-08 View4

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