N. Cho

发表

Inline critical boron concentration search with p-CMFD feedback in whole-core continuous-energy Monte Carlo simulation

Y. Jo, N. Cho, 2018, Annals of Nuclear Energy.

Analytic Function Expansion Nodal Method for Multigroup Diffusion Equations in Cylindrical (r,θ,z) Geometry

Jaejun Lee, N. Cho, 2008 .

A new derivation of the multigroup transport equations via homogeneity and isotropy restoration theory

YuGwon Jo, Nam Zin Cho, Y. Jo, 2017 .

A Proposed New Framework for Nuclear Reactor Physics Analysis with Transport Calculation – Invited –

N. Cho, 2018 .

ON SOME OUTSTANDING PROBLEMS IN NUCLEAR REACTOR ANALYSIS

N. Cho, 2012 .

Comparison of 1-D/1-D Fusion Method and 1-D/1-D Hybrid Method in Two-Dimensional Neutron Transport Problems: Convergence Analysis and Numerical Results

N. Cho, Seungsu Yuk, 2016 .

Coarse-Mesh Angular Dependent Rebalance Acceleration of the Discrete Ordinates Transport Calculations

N. Cho, Y. Park, 2004 .

Two-temperature homogenized model for steady-state and transient thermal analyses of a pebble with distributed fuel particles

Nam Zin Cho, Jong Woon Kim, Hui Yu, 2009 .

Steady- and Transient-State Analyses of Fully Ceramic Microencapsulated Fuel with Randomly Dispersed Tristructural Isotropic Particles via Two-Temperature Homogenized Model—I: Theory and Method

Yoonhee Lee, N. Cho, Bumhee Cho, 2016 .

Few-group condensation via two-material coexisting ring model for fast reactor core analysis

N. Cho, Jong Hyuck Won, 2015 .

Nuclear-Thermal Analysis of Fully Ceramic Microencapsulated Fuel with Randomly Dispersed TRISO Particles via Two-Temperature Homogenized Model

Yoonhee Lee, N. Cho, 2015 .

Steady- and transient-state analyses of fully ceramic microencapsulated fuel loaded reactor core via two-temperature homogenized thermal-conductivity model

Yoonhee Lee, N. Cho, 2015 .

Three-dimensional single-channel thermal analysis of fully ceramic microencapsulated fuel via two-temperature homogenized model

Yoonhee Lee, N. Cho, 2014 .

Particle Transport Monte Carlo Method for Heat Conduction Problems

N. Cho, 2011 .

Fine-lattice stochastic modeling of particle fuels in an HTGR unit fuel element

N. Cho, H. Yu, 2005 .

Two-Temperature Homogenized Model for Thermal Analysis of a Pebble with Distributed Fuel Particles

N. Cho, H. Yu, 2008 .

Temperature distributions in a pebble with dispersed fuel particles calculated by Monte Carlo method

J. Song, N. Cho, 2008 .

Comparison of Iron(Fe) Data of ENDF/B-IV and VI in Yonggwang Nuclear Unit-3/4 Vessel Fluence Calculation

Nam Zin Cho, Tae Hyeong Kim, N. Cho, 1995 .

Nonlinear Analytic and Semi-Analytic Nodal Methods for Multigroup Neutron Diffusion Calculations

Xuedong Fu, N. Cho, 2002 .

Depletion analysis of a solid-type blanket design for ITER

Nam Zin Cho, Seungyon Cho, Mu-Young Ahn, 2008 .

Global depletion analysis of Korean helium cooled solid breeder TBM model for demo fusion reactor

M. Ahn, Seungyon Cho, S. Yun, 2010 .

Feasibility of Graphite Reflector in Tritium Breeding Blanket

D. Ku, M. Ahn, Seungyon Cho, 2010 .

Global/local iterative methods for equivalent diffusion theory parameters in nodal calculation

Nam Zin Cho, Hark Rho Kim, N. Cho, 1993 .

Whole-Core Transport Solutions with 2-D/1-D Fusion Kernel via p-CMFD Acceleration and p-CMFD Embedding of Nonoverlapping Local/Global Iterations

N. Cho, Seungsu Yuk, 2015 .

Whole-core transport solution via deterministic S-N transport/p-CMFD overlapping local/global calculation in hexagonal geometry problem

N. Cho, H. Yoo, Muhammad Imron, 2015 .

Overlapping Local/Global Iteration Framework for Whole-Core Transport Solution

S. Yun, N. Cho, Seungsu Yuk, 2013 .

ON SOME OUTSTANDING PROBLEMS IN NUCLEAR REACTOR ANALYSIS

N. Cho, 2012 .

Performance of the Discrete Ordinates Method-Like Neutron Transport Computation with Equivalent Group Condensation and Angle-Collapsing

N. Cho, Jong Hyuck Won, H. Yoo, 2011 .

A STUDY OF THE MULTIPLICITY OF POWER DISTRIBUTIONS IN A NUCLEAR-REACTOR SUBJECT TO REACTIVITY FEEDBACKS

C. Y. Yang, N. Cho, 1989 .

CRX: A code for rectangular and hexagonal lattices based on the method of characteristics

Ser Gi Hong, Nam Zin Cho, S. Hong, 1998 .

Coarse-Mesh Angular Dependent Rebalance Acceleration of the Method of Characteristics in x-y Geometry

N. Cho, Y. Park, 2008 .

Acceleration and Real Variance Reduction in Continuous-Energy Monte Carlo Whole-Core Calculation via p-CMFD Feedback

Y. Jo, N. Cho, 2018 .

Efficient and accurate depletion calculations via two-block decomposition of nuclide concentration vector

Yoonhee Lee, N. Cho, 2013 .

The simplified P{sub 2} approximation implemented in the AFEN diffusion nodal code

J. Noh, N. Cho, K. Moon, 1995 .

Current status of design and analysis of Korean Helium-Cooled Solid Breeder Test Blanket Module

Nam Zin Cho, Ki Jung Jung, Seungyon Cho, 2008 .

Determination of performance criteria at hierarchical levels in a nuclear power plant

Nam Zin Cho, Song K. Sung, N. Cho, 1989 .

FUNDAMENTALS AND RECENT DEVELOPMENTS OF REACTOR PHYSICS METHODS

Nam Zin Cho, N. Cho, 2005 .

Hybrid of AFEN and PEN methods for multigroup diffusion nodal calculation

J. Noh, N. Cho, 1995 .

A new approach of analytic basis function expansion to neutron diffusion nodal calculation

Nam Zin Cho, Jae Man Noh, J. Noh, 1994 .

Kinetics Calculation Under Space-Dependent Feedback in Analytic Function Expansion Nodal Method via Solution Decomposition and Galerkin Scheme

Nam Zin Cho, Do Sam Kim, N. Cho, 2002 .

Design of a nonlinear model-based controller with adaptive PI gains for robust control of a nuclear reactor

Nam Zin Cho, Moon-Ghu Park, Moon‐Ghu Park, 1992 .

A Study of Neutronics Effects of the Spacer Grids in a Typical PWR via Monte Carlo Calculation

Nam Zin Cho, Xuan Bach Tran, N. Cho, 2016 .

Daubechies’ Wavelet Method for Angular Solution of the Neutron Transport Equation

Youqi Zheng, Nam Zin Cho, Liangzhi Cao, 2010 .

Analytic initialization of nonequilibrium iodine and xenon distributions for core transient simulation

S. Zee, N. Cho, J. Song, 1996 .

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

N. Cho, Keon Woo Park, 2001 .

A New Acceleration Method of Additive Angular Dependent Rebalance with Extrapolation for Discrete Ordinates Transport Equation

N. Cho, C. J. Park, 2002 .

Nonoverlapping local/global iterations with 2-D/1-D fusion transport kernel and p-CMFD wrapper for transient reactor analysis—II: Parallelization and Predictor–Corrector Quasi-Static method application

Nam Zin Cho, Bumhee Cho, N. Cho, 2016 .

Fusion of method of characteristics and nodal method for 3-D whole-core transport calculation

N. Z. Cho, N. Cho, 2002 .

Partial current-based CMFD acceleration of the 2D/1D fusion method for 3D whole-core transport calculations

Nam-Zin Cho, C. J Park, G. S Lee, 2003 .

Generation of Spatial Weighting Functions for Ex-Core Detectors by Adjoint Transport Calculation

Nam Zin Cho, Joonhong Ahn, Joon Gi Ahn, 1992 .

A core design concept for multi-purpose research reactors

N. Cho, C. Seo, 2012 .

A nonoverlapping local/global iterative method with 2-D/1-D fusion transport kernel and p-CMFD wrapper for transient reactor analysis

Nam Zin Cho, Bumhee Cho, N. Cho, 2015 .

2D/1D fusion method solutions of the three-dimensional transport OECD benchmark problem C5G7 MOX

Nam Zin Cho, G. S Lee, N. Cho, 2006 .

The Analytic Function Expansion Nodal Method Refined with Transverse Gradient Basis Functions and Interface Flux Moments

Nam Zin Cho, Sweng Woong Woo, Jae Man Noh, 2001 .

ESTIMATION OF NEUTRON FLUX AND XENON DISTRIBUTIONS VIA OBSERVER-BASED CONTROL THEORY

Nam Zin Cho, Young Ho Park, N. Cho, 1992 .

On a New Acceleration Method for 3D Whole-Core Transport Calculations

N. Cho, C. J. Park, G. Lee, 2003 .

Two-Level Convergence Speedup Schemes for p-CMFD Acceleration in Neutron Transport Calculation

Nam Zin Cho, Seungsu Yuk, N. Cho, 2017 .

Acceleration of source convergence in Monte Carlo k-eigenvalue problems via anchoring with a p-CMFD deterministic method

S. Yun, N. Cho, 2010 .

Improved Two-Level p-CMFD Acceleration in Neutron Transport Calculation

N. Cho, Seungsu Yuk, 2017 .

Analytic Modeling of the Xenon Oscillation Due to Control Rod Movement

S. Zee, N. Cho, J. Song, 1999 .

Two-group, flux-coupled xenon oscillation model with an equation system of axial difference parameters

Nam Zin Cho, Jae Seung Song, N. Cho, 1997 .

Time-optimal control of nuclear reactor power with adaptive proportional-integral-feedforward gains

Nam Zin Cho, Moon-Ghu Park, N. Cho, 1993 .

Optimal control for xenon spatial oscillations in load follow of a nuclear reactor

Nam Zin Cho, Lawrence M. Grossman, L. Grossman, 1983 .

Whole-core depletion calculation using domain decomposed continuous-energy Monte Carlo simulation via McBOX with p-CMFD acceleration and inline feedback

Yonghee Kim, HyeonTae Kim, Y. Jo, 2020 .

Preliminary safety analysis of Korea Helium Cooled Solid Breeder Test Blanket Module

Nam Zin Cho, Seungyon Cho, Mu-Young Ahn, 2008 .

Feasibility study of a dedicated nuclear desalination system: Low-pressure Inherent heat sink Nuclear Desalination plant (LIND)

Jeong Ik Lee, Hee Cheon No, Jin Young Choi, 2015 .

Nuclear Reactor Transient Analysis by Continuous-Energy Monte Carlo Calculation Based on Predictor-Corrector Quasi-Static Method

YuGwon Jo, Nam Zin Cho, Bumhee Cho, 2016 .

Fission and Surface Source Iteration Method for Domain Decomposed Monte Carlo Whole-Core Calculation

Y. Jo, N. Cho, 2016 .

The Analytic Function Expansion Nodal (AFEN) Method with Half-Interface Averaged Fluxes in Mixed Geometry Nodes for Analysis of Pebble Bed Modular Reactor (PBMR) Cores

Do Sam Kim, N. Cho, 2003 .

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

N. Cho, Keon Woo Park, 2001 .

Graphite-filled mixed-oxide fuel design for fully loaded PWR cores

Nam Zin Cho, Chang Keun Jo, Yonghee Kim, 2000 .

Acceleration of the Analytic Function Expansion Nodal method by two-factor two-node nonlinear iteration

J. Noh, S. Hong, N. Cho, 1999 .

A spectral-Galerkin coarse-mesh approach to solving the two-dimensional multigroup diffusion equations

N. Cho, Hong Cheng, 1997 .

Extension of analytic function expansion nodal method to multigroup problems in hexagonal-Z geometry

Nam Zin Cho, Yonghee Kim, Yonghee Kim, 1997 .

Analytic function expansion nodal method for hexagonal geometry

Nam Zin Cho, Jae Man Noh, J. Noh, 1995 .

COMPARATIVE ANALYSIS OF STATIC AND KINETIC CALCULATIONAL FEATURES IN THE ANALYTIC FUNCTION EXPANSION NODAL METHOD

D. S. Kim, N. Cho, 2002 .

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

J. Noh, S. Woo, N. Cho, 2000 .

Analytic Function Expansion Nodal (AFEN) Method in Hexagonal-Z Three-Dimensional Geometry for Neutron Diffusion Calculation

Jaejun Lee, N. Cho, 2006 .

Improved Features of the AFEN Method in Hexagonal-Z 3-D Geometry for Neutron Diffusion Calculation

C. Y. Yang, Jaejun Lee, J. Jo, 2005 .

New features of the analytic function expansion nodal (AFEN) method and implementation in the hexagonal-Z KORDAX code

Jong Chull Jo, Nam Zin Cho, Jaejun Lee, 2004 .

Acceleration of Three-Dimensional AFEN Nodal Codes via Coarse Group Rebalance and Direct Matrix Inverse

Nam-Zin Cho, D. S Kim, D. S. Kim, 1999 .

SOME OUTSTANDING PROBLEMS IN NEUTRON TRANSPORT COMPUTATION

Jonghwa Chang, Nam Zin Cho, Jonghwa Chang, 2009 .

Development of the public attitude model toward nuclear power in Korea

Nam Zin Cho, Young Sung Choi, Young-sung Choi, 1998 .

The infinite medium Green's function method for multigroup discrete ordinates transport problems in multi-layered slab geometry

S. Hong, N. Cho, 2001 .