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가 나 다 라 마 바 사 아 자 차 카 타 파 하

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

Thesis Issue Date2023-02 View11

Computational Shielding Analysis for Marine Long-Life Fast Reactor using Monte-Carlo Code File File

Yossavorn Iangleard

Thesis Issue Date2022-08 View5

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

Thesis Issue Date2022-08 View9

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

Jeong, Sanggeol

Thesis Issue Date2018-08 View3

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

Thesis Issue Date2019-02 View6

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

Tran, Tuan Quoc

Thesis Issue Date2023-08 View12

Development of a Spent Nuclear Fuel Radiation Source Term Framework File File

Bamidele Ebiwonjumi

Thesis Issue Date2022-02 View2

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

Thesis Issue Date2024-02 View8

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

Thesis Issue Date2023-08 View12

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

Thesis Issue Date2023-08 View12

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

Thesis Issue Date2017-02 View8

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

Thesis Issue Date2018-08 View7

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

Mai, Nhan Nguyen Trong

Thesis Issue Date2024-02 View15

Establishment and Application of Diamond Detector Analysis System File

Thesis Issue Date2020-02 View6

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

Thesis Issue Date2020-02 View6

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

Azamat Khassenov

Thesis Issue Date2018-08 View8

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

Khang Hoang Nhat Nguyen

Thesis Issue Date2019-08 View4

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

Thesis Issue Date2019-02 View8

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

Thesis Issue Date2018-08 View6

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

TUNG DONG CAO NGUYEN

Thesis Issue Date2023-02 View13

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