Browse "NE-Conference Papers(학술회의논문)" by Author 546

Showing results 116 to 175 of 205

116
Gaussian Function Neural Network-Based Self-Tuning control of KMRR

Park, M.G; Cho, Nam-Zin, Proc. of the Korean Nuclear society Spring Meeting, pp.297 - 302, 1993-05

117
Generating Nonnegative Multigroup Scattering Cross Sections with Monte Carlo Simulation

Kim, Jong Woon; Cho, Nam-Zin, Proc. of the Korean Nuclear Society, 2005-05

118
Generation of Gamma-Ray Streaming Kernels Through Cylindrical Ducts via Monte Carlo Method

Kim, D.S; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Spring Meeting, pp.667 - 672, 1992-05

119
Generation of Isotropic and Anisotropic Scattering Cross Sections for Boltzmann-Fokker- Planck Equation via Decomposition and Minimized RMS Errors

Kim, J.W; Cho, Nam-Zin, Proc. of the Korean Nuclear Society, 2001-10

120
Generation of Spatial Weighting Functions for Ex-Core Detectors by Adjoint Transport Calculation

Ahn, J.G; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Spring Meeting, pp.15 - 20, 1992-05

121
Generation of the Analytic Solutions of the Multigroup Discrete Ordinates Transport Equation in Slab Geometry by Using Infinite Medium Green's Function

Hong, S.G; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Autumn Meeting, v.1, pp.47 -, 1999-10

122
Image Reconstruction in Emission Computed Tomography via Multigrid Wavelet-Based Natural Pixel Method

Park, C.J; Cho, Nam-Zin, International Conference on the Physics of Nuclear Science and Technology, pp.1703 -, 1998-10

123
Implementation of a Parallel Algorithm in 2-D Assembly Transport Calculation on a Transputer

Cho, Nam-Zin; Song, J.S, Proc. of the International Symposium on Numerical Transprot Theory, Moscow, Russia, pp.72 - 75, 1992-05

124
Improved features and verification of an AFEN method code in hexagonal-z 3-D geometry for neutron diffusion calculation

Cho, N.Z.; Lee, J.; Kim, D.S.; Yang, C.Y.; Cho, Nam-Zin, 2005 Annual Meeting - American Nuclear Society, v.92, pp.514 - 516, 2005-06-05

125
Improved Features of the AFEN Method in Hexagonal-Z 3-D Geometry for Neutron Diffusion Calculation

Cho, Nam-Zin; Lee, Jaejun; Kim, Do Sam; Yang, Chae Yong; Jo, Jong Chull, Atomic Energy Society of Japan Spring Meeting, pp.391 - 391, 2005-03

126
Improved Negative Fixup with Cell Rebalance for Boltzmann-Fokker-Planck Transport Equation

Choi, Y.K; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Spring Meeting, 2001-05

127
Infinite-Dimensional Observer Theory for Dynamic Estimation of Neutron Flux and Xenon Distributions

Park, Y.H; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Autumn Annual Meeting, pp.131 - 136, 1991-10

128
Inter-Assembly Thermal Flux Gradient Correction of Homogenization Parameters Based on One-Dimensional Heterogeneous Interface Model

Noh, J.M; Joo, H.K; Yoo, J.W; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Spring Meeting, 2001-05

129
Intranodal Burnup Gradient Correction in Analytic Function Expansion Nodal (AFEN) Method

Noh, J.M; Cho, Nam-Zin, International Conference on the Mathematics and Computations, Reactor Physics, and Environmental Analyses, pp.1435 - 1444, 1995-04

130
KIGEN - A Computer Code for Decay Heat Calculation by Analytic Relations

Cho, Nam-Zin; Lee, Y.J, Proc. of the Korean Nuclear Society Spring Annual Meeting, 1990-05

131
MARADD - A Computer Code for Semi-Markov Reliability Analysis of Test/Repair Policies for Standby Safety Systems

Jung, W.S; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Annual Meetign, 1989-05

132
MARAS - A Computer Code for Semi-Markov Reliability Analysis of Alternating Systems

Lee, K.N; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Annual Meeting, 1989-05

133
Maximum Entropy Method for the Reconstruction Problem in Nodal Calculation : Preliminary Results

Na, W.J; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Annual Meeting, 1989-05

134
Molecular Dynamics Simulation of Thermomechanical Properties of Mononitride Nuclear Fuel

Hong, Qian; Cho, Nam-Zin, Proc. of the Korean Nuclear Society, 2005-05

135
Monte Carlo anchoring method for loosely-coupled k-eigenvalue problems

Yun, S.; Cho, Nam-Zin, International Conference on Mathematics, Computational Methods and Reactor Physics 2009, M and C 2009, v.3, pp.1977 - 1990, 2009-05-03

136
Monte Carlo Simulation Models for Randomly Distributed Particle Fuels with Packing Fraction Variability Based on a Sub-Fine Lattice System

Cho, Nam-Zin; Hui, Yu, 2007 Annual Meeting of the Atomic Energy Society of Japan, 2007-03

137
Monte Carlo space-time reactor kinetics method and its verification with time-dependent SN method

Yun, S.; Kim, J.W.; Cho, Nam-Zin, International Conference on the Physics of Reactors 2008, PHYSOR 08, pp.739 - 746, 2008-09-14

138
Multi-Recycleing of Spent Fuel with Low Proliferation Risk

Greenspan, E; Cho, Nam-Zin; Hong, S.G; Kim, T.H; Kastenberg, W.E., International Conference on Emerging Nuclear Energy System, 1998-06

139
Multigrid Wavelet-Based Natural Pixel Method for Image Reconstruction in Emission Computed Tomography

Park, C.J; Park, J.H; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Spring Meeting, v.2, pp.705 - 710, 1998-05

140
Neutron Transport Assembly Calculation with Non-Zero Net Current Boundary Condition for Group Constant Generation

Cho, Nam-Zin; Jo, C.K., Internation Conference on Reactor Physics and Reactor computations, 1994-01

141
Neutronic Analysis of the KSTAR Tokamak Using Beowulf Cluster

Park, J.H; Cho, Nam-Zin; Kim, J, Ninth International Conference on Radiation Shielding, pp.c2-16 -, 1999-10

142
Neutronic Design Approach to a Small Medical Reactor for BNCT

Cho, Nam-Zin, Proceedings of the 2000 Workshop on the Utilization of Research Reactors, 2000-11

143
New features of the analytic function expansion nodal (AFEN) method and implementation in the hexagonal-Z KORDAX code

Cho, Nam-Zin; Lee, J.; Kim, D.S.; Yang, C.Y.; Jo, J.C., 2004 Winter Meeting - American Nuclear Society, v.91, pp.257 - 260, 2004-11-14

144
Nonlinear Model-Based Robust Control of a Nuclear Reactor Using Adaptive PIF Gains and Variable Structure Controller

Park, M.G; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Autumn Meeting, pp.285 - 290, 1992-10

145
Nuclear and thermal analysis of shell-fuel pebble design based on the two-temperature homogenized model

Yu, H.; Cho, Nam-Zin, 2009 ANS Annual Meeting and Embedded Topical Meeting: Nuclear and Emerging Technologies for Space, NETS 2009, v.100, pp.623 - 626, 2009-06-14

146
Nuclear Data Compression and Reconstruction via Discrete Wavelet Transform

Park, Y.R; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Autumn Meeting, pp.245 - 250, 1997-10

147
Nuclear Energy Policy and R&D Prospects: The Korean Case

Cho, Nam-Zin, Proc. of the International Conference on the Physics of Reactors:Operation, Design and Computation21, 1996-09

148
On a New Acceleration Method for 3D Whole-Core Transport Calculations

Cho, Nam-Zin; Lee, G.S; Park, C.J, Annual Meeting of the Atomic Energy Society of Japan, 2003-03

149
On the AFEN Method for Triangular Nodes in Hexagonal Assembly Cores

Cho, Nam-Zin; Kim, D.S., Proc. of the Korean Nuclear Society Spring Meeting, pp.25 - 30, 1995-05

150
On the Multiplicity of Power Distributions in a Nuclear Reactor under Reactivity Feedback Effects

Yang, C.Y; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Annual Meeting, 1987-10

151
One-Dimensional Heterogeneous Interface Model for Inter-Assembly Thermal Flux Gradient Correction of Homogenization Parameters

Noh, J.M; Joo, H.K; Yoo, J.W; Cho, Nam-Zin, ANS Interanational Meeting on Mathematical Methods for Nuclear Applications (M&C 2001), 2001-09

152
Online Self-Tuning Control of Korea Multipurpose Research Reactor Based on Gaussian Function Neural Network,

Park, M.G.; Cho, Nam-Zin, Asian Symposium on Research Reactors, pp.157 - 166, 1993-11

153
Optimal Control of Xenon Concentration via Observer Design

Woo, H.S; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Annual Meeting, 1989-05

154
Overlap local/global iteration framework for Monte Carlo/diffusion nodal calculations

Yun, S.; Lee, J.; Cho, Nam-Zin, 2010 ANS Annual Meeting and Embedded Topical Meetings, pp.528 - 532, 2010-06-13

155
Pair Importance Measures in systems Analysis

Youngblood, R; Xue, D; Cho, Nam-Zin, Proc. of the International ANS/ENS Topical Meeting on Thermal Reactor Safety, San diego, California, v.2, pp.1 - 7, 1986-02

156
Parallel Schwarz Algorithm for the Neutron Diffusion Equation on an MIMD Architecture

Kim, Y.H; Cho, Nam-Zin, International Conference on Mathematical Methods and Supercomputing in Nuclear Applications, v.2, pp.100 - 111, 1993-04

157
Parallel Sn Transport Calculation on a Transputer Network

Kim, Y.H; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Spring Meeting, pp.29 - 34, 1994-05

158
Pin Power Reconstruction from the HANARO Fuel Assembly Gamma Scanning

Seo, C.G; Park, C.J; Cho, Nam-Zin; Kim, H.R, Proc. of the Korean Nuclear Society Autumn Meeting, pp.56 -, 1998

159
Pin Power Reconstruction of HANARO Fuel Assembly via Gamma Scaning

Cho, Nam-Zin; Fujine, S; Kobayashi, H; Kanda, K, Neutron Dadiography(6), pp.591 -, 2001

160
Policies and Technology Development For the Nuclear Fuel Cycle in Korea

Cho, Nam-Zin, College of Engineering Industrial Liaison Program 19th Annual Conference, pp.21 -, 1997-03

161
Power Distributions in a Nuclear Reactor Core Under Various Operating Conditions and Their Safety Implications

Yang, C.Y; Cho, Nam-Zin, Proc. of the international ENS/ANS Conference on thermal Reactor Safety, Avignon, France, v.4, pp.1314 - 1323, 1988-10

162
Preconditioners for Krylov Iterative Method for Two-Dimensional MOC Problems

Yoo, Han Jong; Cho, Nam-Zin, Proceedings of the Korean Nuclear Society, 2007-10

163
Preliminary Analysis on Decay Heat Removal Capability of Helium Cooled Solid Breeder Test Blanket Module

Ahn, M.Y.; Cho, S.; Kim, D.H.; Lee, E.S.; Kim, H.S.; Suh, J.S.; Yun, S; et al, Proceedings of the Korean Nuclear Society, 2007-10

164
Probabilistic Safety Criteria (PSC) Allocation for Optimum Design and Operation of a Nuclear Power Plant

Cho, Nam-Zin; Jung, W.S, Proceedings of the First Korea/Japan Joint Workshop on Probabilistic Safety Assessment (PSA), 1992-11

165
Progress in the Design of a Tritium Breeding Blankets for Testing in ITER

Hong, BG; In, WK; Kim, Y; Lee, DW; Song, KW; Yoo, KH; Cho, S; et al, 21st IAEA Fusion Energy Conference, 2006-10

166
Quantification of minimal cutset truncation errors in fault tree analysis

Choi, J.S.; Cho, Nam-Zin, 2006 Annual Meeting - American Nuclear Society, pp.180 - 182, 2006-06-04

167
Reactivity Condition Monitoring Via Wavelet Transform De-noising

Park, C.J; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Autmn Meeting, v.1, pp.67 - 72, 1996-11

168
Reactor Physics and Nuclear Engineering Education in Korea

Cho, Nam-Zin, Advances in Reactor Physics and Mathematics and Computation into the Next Millennium (PHYSOR 2000), pp.XIV.A.-7 -, 2000-05

169
Reactor Physics in KOREA and Related Topics

Cho, Nam-Zin, Proceedings of the Atomic Energy Society of Japan Fall Meeting, 2000-09

170
Reconstruction of Pointwise Neutron Flux Distribution via Minimum Cross-Entropy Principle

Jung, W.S; Cho, Nam-Zin, Proc. of the International Topical Meeting on Advances in Mathmatics, Computation, and Reactor Physi, pp.1 - 12, 1991-04

171
Refinement of Monte Carlo anchoring method tested on continuous-energy loosely-coupled fissile problems

Yun, S.; Cho, Nam-Zin, International Conference on the Physics of Reactors 2010, PHYSOR 2010, pp.591 - 604, 2010-05-09

172
Reliability Allocation in Nuclear Power Plants

Bari, R.A; Cho, Nam-Zin; Papazoglou, I.A, Transaction of the 8th International Conference on Structural Mechanics in Reactor Technology, 1985-08

173
Reliability Analysis of the Reactor Protection System Using Markov Processes

Cho, Nam-Zin, Nuclear Engineering and Technology, v.19, no.4, pp.279 - 291, Korean Nuclear Society, 1987-12

174
Semi-Analog Monte Carlo (SMC) Method for Time-Dependent Three-Dimensional Heterogeneous Radiative Transfer Problems

Yun, S.H; Cho, Nam-Zin, Proc. of the Korean Nuclear Society, 2003-10

175
SLIM/SVD - A Computer Code for Evaluation of System-Level Importance Measures in Probabilistic Safety Analysis of Nuclear Power Plants

Jung, W.S; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Annual Meeting, 1988-05

rss_1.0 rss_2.0 atom_1.0