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

KorawitSaeju

Thesis Issue Date2022-08 View12

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

Jeong, Sanggeol

Thesis Issue Date2018-08 View6

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

Tak, Taewoo

Thesis Issue Date2017-02 View16

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 View13

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

Mai, Nhan Nguyen Trong

Thesis Issue Date2024-02 View32

Establishment and Application of Diamond Detector Analysis System File

Kong, Chidong

Thesis Issue Date2020-02 View8

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

Kim, Mi Jin

Thesis Issue Date2020-02 View9

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 View12

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 View10

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

Kim, Ji Hyeon

Thesis Issue Date2019-02 View12

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

Cho, Tae Won

Thesis Issue Date2018-08 View10

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

TUNG DONG CAO NGUYEN

Thesis Issue Date2023-02 View21

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 View14

New Burnable Absorber and Zirconium Reflector for Advanced PWRs File File

Choe, Jiwon

Thesis Issue Date2015-08 View26

Pin-based Pointwise Energy Slowing-down Method for Resonance Self-shielding Calculation File File

Choi, Sooyoung

Thesis Issue Date2017-02 View36

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 View10

The initial implementation of MCS on graphics processing unit using CUDA fortran File

Park, Jeehoon

Thesis Issue Date2024-02 View35

Verification and Validation for Transient Calculation of STREAM/RAST-K 2.0 File File

Jeong, Eun

Thesis Issue Date2018-08 View13

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 View19

Verification of STREAM3D for APR1400 Reactor Core Benchmark File File

RanLee

Thesis Issue Date2022-08 View26

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