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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

Rahman, Anisur

Thesis Issue Date2023-02 View98
Axial Function Based on an Asymmetric 4-Point Finite Difference Method for 3D MOC/DD Neutron Transport Calculations File

Lee, Woonghee

Thesis Issue Date2025-08 View225
Cobalt self-powered neutron detector calculation Affected by control rod Based on Monte Carlo simulation File

Lee, Wongyu

Thesis Issue Date2024-08 View102
Computational Shielding Analysis for Marine Long-Life Fast Reactor using Monte-Carlo Code File File

Yossavorn Iangleard

Thesis Issue Date2022-08 View108
Deep Neural Network for Generating Homogenized Fuel Assembly Data for Nodal Codes File File

KorawitSaeju

Thesis Issue Date2022-08 View79
Design of High Density Spent Fuel Storage Rack Applying Burnup Credit File File

Jeong, Sanggeol

Thesis Issue Date2018-08 View75
Development of a GPU-Based Time-Dependent Monte Carlo Code System for High-Fidelity Large- Scale Nuclear Reactor Transient Analysis File File

Jeong, Eun

Thesis Issue Date2024-08 View222
Development of a new GPU-optimized Monte Carlo code for Fresh Fuel Pressurized Water Reactor Analysis and Design File

Muhammad Rizwan Ali

Thesis Issue Date2025-02 View88
Development of a New Monte Carlo Code for High-Fidelity Power Reactor Analysis File File

Lee, Hyunsuk

Thesis Issue Date2019-02 View85
Development of a Nodal Diffusion Code for Fast Reactor Analysis and Design File

Tran, Tuan Quoc

Thesis Issue Date2023-08 View77
Development of a Spent Nuclear Fuel Radiation Source Term Framework File File

Bamidele Ebiwonjumi

Thesis Issue Date2022-02 View71
Development of Adjoint Flux Calculation Technique for Exact Perturbation Theory in Monte Carlo Transport File

Jo, Yunki

Thesis Issue Date2024-08 View99
Development of Advanced Cross-Section Model including Control Rod Depletion for Soluble Boron-Free SMR Operation File

Park, Jinsu

Thesis Issue Date2024-08 View150
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 View86
Development of Nodal Diffusion Code for VVER and HTGR analysis with Advanced Semi Analytic Nodal Method File File

Jang, Jaerim

Thesis Issue Date2023-08 View105
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 View88
Development of Resonance Treatment Methods for AIC Control Rod in Nuclear Reactor Application File

Kim, Wonkyeong

Thesis Issue Date2024-08 View122
Development of Ultra-long Cycle Small Modular Sodium-cooled Fast Reactor Core Concept File File

Tak, Taewoo

Thesis Issue Date2017-02 View98
Enhanced Accident Performance of Zirconium Alloy Cladding Tube by High-Temperature Preformed Oxide and Analysis of Preformed Oxide Microstructures File File

Lee, Cheol Min

Thesis Issue Date2018-08 View83
Enhanced Fidelity of Monte Carlo Coupled Multi-Physics Simulations for Light Water Reactors File

Muhammad Makrus Imron

Thesis Issue Date2025-02 View117
Enhancing the energy deposition model in STREAM with photon transport module File

Mai, Nhan Nguyen Trong

Thesis Issue Date2024-02 View162
Establishment and Application of Diamond Detector Analysis System File

Kong, Chidong

Thesis Issue Date2020-02 View60
Gd and B Based Integral Neutron Absorber for Spent Fuel Transportation and Storage System File

Kim, Mi Jin

Thesis Issue Date2020-02 View65
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 View86
GPU-Optimized CMFD-Based Transient Fixed Source Solution for STREAM-3D File

MOHANTY, SAISUNDAR

Thesis Issue Date2026-02 View11
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 View55
Investigation of ZrN Non-Reactively Sputtered Diffusion Barrier Coating for U-Mo Dispersion Fuel File File

Kim, Ji Hyeon

Thesis Issue Date2019-02 View69
Measurements and Modeling of Thermal Conductivity of U-Mo/Al Dispersion Fuel for Research Reactor File File

Cho, Tae Won

Thesis Issue Date2018-08 View58
Monte Carlo Code MCS as Cross-section Generation Tool for Reactor Core Analysis File File

TUNG DONG CAO NGUYEN

Thesis Issue Date2023-02 View69
Neutron XS Library Generation of ENDF/B-VIII.0 for MOC code STREAM and Monte Carlo code MCS File File

Kim, Kiho

Thesis Issue Date2019-08 View60
New Burnable Absorber and Zirconium Reflector for Advanced PWRs File File

Choe, Jiwon

Thesis Issue Date2015-08 View75
Optimization of a 3D neutron transport code STREAM for highly parallel execution using Graphics Processing Units File

Dzianisau, Siarhei

Thesis Issue Date2025-08 View56
Pin-based Pointwise Energy Slowing-down Method for Resonance Self-shielding Calculation File File

Choi, Sooyoung

Thesis Issue Date2017-02 View133
Steady-State Analysis of the APR1400 Benchmark using STREAM/RAST-K Two-step code File File

Chouchene, Yassine

Thesis Issue Date2024-08 View119
The Angle-dependent Linear Source Approximation for the Three-Dimensional Method of Characteristics/Diamond-Differencing Neutron Transport Simulation File File

Choe, Jiwon

Thesis Issue Date2021-08 View64
The initial implementation of MCS on graphics processing unit using CUDA fortran File

Park, Jeehoon

Thesis Issue Date2024-02 View149
Verification and Validation for Transient Calculation of STREAM/RAST-K 2.0 File File

Jeong, Eun

Thesis Issue Date2018-08 View64
Verification and Validation of Monte Carlo Code MCS for the Multi-physics High-fidelity Analysis of OPR-1000 Multi-cycle Operation File File

Vutheam Dos

Thesis Issue Date2020-08 View60
Verification of STREAM3D for APR1400 Reactor Core Benchmark File File

RanLee

Thesis Issue Date2022-08 View138
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