Ph.D. Theses

 

Name

Thesis Title

Year

Jong Tae Lee

A Cell-Homogenization Method for Strongly Heterogeneous Research Reactors

1991. 2

Young Ho Park

Estimation and Control of Space-Dependent Reactor Cores via Observer-Based Control Theory

1992. 2

Chae Yong Yang

Nonlinear Stability Analysis of Nuclear Reactors - Expansion Methods for Stability Domains

1992. 8

Moon Ghu Park

Robust Nonlinear Control of Nuclear Reactors Under Model Uncertainty

1993. 8

Woo Sik Jung

Determination of Performance Criteria of Safety Systems in a Nuclear Power Plant via Simulated Annealing Optimization Method

1993. 8

Hark Rho Kim

Global/Local Iterative Homogenization Methods for Neutron Diffusion Nodal Theory

1994. 2

Yong Hee Kim

Parallel Algorithms for Nuclear Reactor Analysis via Domain Decomposition Method

1995. 2

Jae Man Noh

Analytic Function Expansion Nodal Method for Nuclear Reactor Core Design

1995. 8

Tae Hyeong Kim

Source Projection Analytic Nodal SN Method for Analysis of Non-Rectangular Assembly Cores

1996. 8

Jae Seung Song

Analytic Initialization Method for Xenon Oscillation in Power Reactor Simulation

1998. 8

Ser Gi Hong

Angular Dependent Rebalance Method for Solving the Neutron Transport Equation

1999. 2

Young Sung Choi

A Study on the Social Risk-Judgment for Nuclear Energy (Development of the Risk-Judgement Model)

1999. 2

Kap Suk Moon

A Fast Converging CMFD Nonlinear Iteration Scheme for Two-Node Analytic Function Expansion Nodal Methodology

2000.2

Hyeong Heon Kim

An Equivalence Relation and Grey Dancoff Factor Calculated by Monte Carlo Method for Irregular Fuel Assemblies

2000.2

Sang Ji Kim

Design of a Pan-Shape Transuranic Burner Core with Low Sodium Void Reactivity

2001.2

Chang Joon Jeong

Fuel Management Method Using Power Mapping and Optimization Theory for CANDU Reactors

2001.2

Chang Keun Jo

Graphite - Filled Mox Fuel Design for Fully Loaded PWR Cores

2001.8

Chang Je Park

Higher-Order Difference Methods for the Solutions of Neutron Diffusion and Transport Equations

2001.8

Keon Woo Park

The p-Version of the Finite Element Method for the Solution of Neutron Diffusion Equations

2002.2

Do Sam Kim

A Solution Decomposition Approach to Reator Kinetics Calculation Under Space-Dependent Feedbacks in the Analytic Function Expasion Nodal Method

2002.2

Seung Woong Woo

Refinement of Analytic Function Expansion Nodal Method with Transverse Gradient Basis Functions and Interface Flux Moments

2002.2

 Sung Goo Chi

H Control Theory Applied to Xenon Control for Load Follow Operation of A Nuclear Reactor

2002.2

 M.S. Theses  

 

Name

Thesis Title

Year

Chae Yong Yang

Investigation of Multiplicity of Power Distributions in a Nuclear Reactor Under Reactivity Feedback Effects

1988. 2

Hun Young Jeong

The Reconstruction of Pointwise Power Distributions in a Light Water Reactor Core from Coarse-Mesh Nodal Calculations

1988. 2

Song Ki Sung

Determination of Intermediate-Level Performance Criteria for a Nuclear Power Plant Based on Reliability and Risk Models

1988. 2

Woo Sik Jung

Semi-Markov Reliability Analysis of Three Test/Repair Polices in a Standby Safety System

1989. 2

Won Joon Na

An Information-Theoretic Approach to the Reconstruction of Pointwise Flux Distribution in Nodal Calculations

1989. 2

Kwang Nam Lee

A Semi-Markovian Approach to Reliability Analysis of the Alternating System

1989. 2

Hae Seuk Woo

Optimal Control of Xenon Concentration in a Nuclear Reactor via Observer Design

1989. 2

Jong Soo Choi

Variance Reduction Techniques for Uncertainty Analysis of Fault Trees

1990. 2

Yu Jong Lee

Summation Calculation of the Nuclear Decay Heat by Analytic Relations 

1990. 2

Yong Hee Kim

An Investigation of the Control Rod Cusping Problem in Nodal Methods

1990. 2

Do Ik Chang

An Analytic Relations Method for the Calculation of Actinides Concentrations

1991. 2

Byung Hyun Park

Development of a Computer Code for Common Cause Failure Analysis

1991. 2

Joon Gi Ahn

Generation of Spatial Weighting Functions for Ex-Core Detectors Using Adjoint Flux

1992. 2

Tae Hyeong Kim

The Reconstruction of Pointwise Neutron Flux Distribution via Minimum Cross-Entropy Method 

1992. 2

Young Chul Cho

Adomian's Decomposition Method Applied to the Reactor Kinetics

1992. 2

Dong Su Kim

Generation of Gamma-Ray Streaming Kernels Through Cylindrical Ducts via Monte Carlo Method

1992. 2

Jae Seung Song

Parallel Processing of Neutron Transport in Fuel Assembly Calculation

1992. 2

Kyung Baek Lee

Nonlinear Stability Analysis of a CANDU Reactor

1993. 2

Chang Keun Jo

Neutron Transport Assembly Calculation with Non-zero Net Current Boundary Condition

1993. 8

Sang Hyun Kim

Finite Moments Approach to the Time-Dependent Neutron Transport Equation

1994. 2

Ser Gi Hong

An Investigation of the Method of Streaming Rays for Radiation Transport Problems

1994. 2

Duck Joon Koh

Relative Mass Resolution Technique for Optimum Design of a Gamma Nondestructive Assay System

1995. 2

Keon Woo Park

Waveform Relaxation Method for Reactor Dynamics

1995. 2

Chang Je Park

Wavelet Theory for Solution of the Neutron Diffusion Equation

1995. 2

Yong Bae Kim

Feasibility Study of a Moderation-Enhanced Reactor Core Loaded 100% with MOX Fuel

1996. 2

Do Sam Kim

AFEN-Polynomial Correction Model for Reactor with Fuel Assemblies Under Burnup Gradient

1996. 2

Jeong Hwan Park

Design of Medical Reactor Generating High Quality Neutron Beams for Boron Neutron Capture Therapy

1997. 2

Sang Hoon Lee

A Hopfield-Like Artificial Neural Network for Solving Inverse Radiation Transport Problems

1997. 2

Kyung Taek Lee

Design and Evaluation of a Thorium Fueled Reactor with Seed-Blanket Assembly Configuration

1998. 2

 Chul Gyo Seo

Reconstruction of the Pin Power Distribution from the HANARO Fuel Assembly Gamma Scanning

  1999. 2

 Young Ryoung Park

Online Compression and Reconstruction of Nuclear Power Plant Signals Using Wavelet Transform

  1999. 2

 Hokyu Ryu

Application of Monte Carlo Method with Forward and Adjoint Midway Coupling to Radiation Transport Calculation

  1999. 2

Gil Soo Lee

Parallelization and Coarse Mesh Rebalance Acceleration of the Method of Characteristics in Neutron Transport Theory

2000.2

Eun Young Han

Design of a Plate Type Fuel Based-Low Power Medical Reactor for Boron Neutron Capture Therapy

2000.2

Sun Doo Kim

Optimization of Fuel Features for Economical Operation of Nuclear Power Plants

2001.2

Jang Eun Moon

Boundary Element Method for Neutron Diffusion Equation with Chebyshev's Equal Weight Integration Formula

2001.2

Sung Bok Lee

Stability Analysis of Coarse Group Rebalance Acceleration for Multigroup Two-Dimensional Diffusion Equations

2001.2

Yoon Keun Choi

Improved Negative Fixup with Cell Rebalance for Boltzman-Fokker-Planck Transport Equation

2001.2

Jong Woon Kim

Generation of Isotropic and Anisotropic Scattering Cross Sections for Boltwmann-Fokker-Planck Equation via Extrapolation Exponential Function and Minimized RMS Errors

2002.2

Dae Han Jung

Spectral Analytic Discrete-Ordinates Transport Method Based on Infinite Medium Green's Function in Linearly Anisotropic Scattering, Multiplying Fission Source Problems

2002.2

 B.S. Theses

 

Name

Thesis Title

Year

Keon Woo Park

Robust Nonlinear Observer-Controller Synthesis for a Nuclear Reactor

1993. 2

Kang Hyun Lee

A Multigrid Algorithm for the Analysis of Nuclear Reactors

1997. 2

Hokyu Ryu

A Study of Using GMRES for Nuclear Reactor Analysis

1997. 2

Young Tae Han

A Multigrid Algorithm for the Analysis of Hexagonal Nuclear Reactor

1998. 2 

Myun Soo Kim

Development of a Parrallel Computer Code for Three-Dimensional Multigroup Neutron Diffusion Equation

2000.2

 Sung Hwan Yun

Delvopment of a Three-Dimensional Neutron Transport Code SUPERTRAN With Discrete Ordinates Method

2002.8