Browse "NE-Conference Papers(학술회의논문)" by Author 546
Showing results 71 to 130 of 205
| Cell Homogenization Method for Strongly Heterogeneous Research Reactors Lee, J.T; Lee, B.H; Cho, Nam-Zin; Oh, S.K, Proc. of the International Topical Meeting on Advanced in Math. Computation, and Reactor Physics, v.3, pp.1 - 12, 1991-04 |
| Chernobyl : Nonlinear Reactor Analysis Revisited Cho, Nam-Zin, Special Lecture, Proc. of the Korean Nuclear Society Annual Meeting, 1987-10 |
| CMADR Acceleration and Its Convergence Analysis of the Method of Characteristics for Neutron Transport Calculation Park, Young Ryong; Cho, Nam-Zin, Nuclear Mathematical and Computational Science M&C 2005, 2005-09 |
| Coarse group rebalance acceleration of the AFEN method solutions in cylindrical (r,罐,z) geometry Lee, J.; Cho, Nam-Zin, 2007 Annual Meeting on American Nuclear Society, pp.497 - 500, 2007-06-24 |
| Coarse mesh rebalance acceleration revisited: Krylov preconditioning Yoo, H.J.; Cho, Nam-Zin, Joint International Topical Meeting on Mathematics and Computations and Supercomputing in Nuclear Applications, M and C + SNA 2007, 2007-04-15 |
| Coarse-Mesh Angular Dependent Rebalance Acceleration Method for Transport Calculations in X-Y Geometry Park, Y.R; Cho, Nam-Zin, 18'th International Conference on Transport Theory, 2003-07 |
| Coarse-Mesh Angular Dependent Rebalance Acceleration Method in X-Y Geometry Park, Y.R; Cho, Nam-Zin, Proc. of the Korean Nuclear Society, 2003-06 |
| Code System Development for Analysis of the Fast Transmutation Reactors Cho, Nam-Zin; Kim, Y.H., Proc. of the Korean Nuclear Society Autumn Meeting, pp.91 - 96, 1995-10 |
| Comparative Analysis of Static and Kinetic Calculational Features in the Analytic Function Expansion Nodal Method Kim, D.S; Cho, Nam-Zin, International Conference on the New Frontiers of Nuclear Technology: Reactor Physics, Safety and High-Performance Computing PHYSOR 2002, 2002-10 |
| Comparison of CMFD and p-CMFD Acceleration Method for Neutron Transport Calculations Cho, Nam-Zin; Lee, G.S., Proc. of the Korean Nuclear Society, 2003-06 |
| Comparison of Coarse Mesh Rebalance and Coarse Mesh Finite Difference Accelerations for the Neutron Transport Calculation Cho, Nam-Zin; Park, C.J., Nuclear Mathematical and Computational Sciences M&C(2003), 2003-04 |
| Comparison of Criticality Benchmark Calculations on the UO2 and MOX Fuel Arrays Using ENDF/B-V and ENDF/B-VI Data Ahn, J.G; Cho, Nam-Zin, Advances in Reactor Physics and Mathematics and Computation into the Next Millennium (PHYSOR 2000), pp.IX.C-1 -, 2000-05 |
| Comparison of LCLS Algorithm and MCNP/CFP Code for Analysis of VHTR Fuel Elements with Randomly Distributed Particles Yun, Sunghwan; Cho, Nam-Zin, Proc. of the Korean Nuclear Society, 2005-05 |
| Comparison of Methods Applicable to Evaluation of Nuclear Power Plant Technical Specifications Cho, Nam-Zin; Bozoki, G.E; Youngblood, R.W, Proc. of the International ANS/ENS Topical engineering on Thermal Reactor Safety, San diego, v.2, pp.1 - 8, 1986-02 |
| Comparison of Monte Carlo simulation models for randomly distributed particle fuels in VHTR fuel elements Yu, H.; Cho, Nam-Zin, 2006 Winter Meeting of the American Nuclear Society, pp.719 - 721, 2006-11-12 |
| Convergence Analysis of CMADR Acceleration for the Method of Characteristics Park, Yong Ryong; Cho, Nam-Zin, Proc. of the Korean Nuclear Society, 2005-05 |
| Convergence Analysis of the Parallel Schwarz Algorithm with Under-Relaxation in Pseudo- Boundary Conditions Kim, Y.H; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Autumn Meeting, Seoul, pp.223 - 228, 1992-10 |
| Criticality Analysis for the Conceptual Spent Fuel Dry Storage with Burnup Credit Kim, Jong Woon; Cho, Nam-Zin; Lee, Sang-Jin; Jang, Hyun Kie, Proceedings of International Symposium on Radiation Safety Management, pp.619 - 628, 2007-11 |
| Criticality Calculation for Cluster Fuel Bundles Using Monte Carlo Generated Grey Dancoff Factor Kim, H.H; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Spring Meeting, v.1, pp.17 -, 1999 |
| CRX : A Characteristic Transport Theory Code for Cell and Assembly Calculations in Reactor Core Design Cho, Nam-Zin; Hong, S.G., Proc. of the Korean Nuclear Society Autumn Meeting, pp.85 - 90, 1995-10 |
| CRX-Hex : A Transport Theory Code Based on Characteristic Method for Hexagonal Geometry Cho, Nam-Zin; Hong, S.G, Proc. of the Korean Nuclear Society Spring Meeting, pp.28 - 33, 1996-05 |
| CRX: A Transport Code for Cell and Assembly Calculations Based on Characteristic Method Cho, Nam-Zin; Hong, S.G., Proc. of the International Conference on the Physics of Reactors:Operation, Design and Computation250, 1996-09 |
| Current Status of Design and Analysis of Korea Helium Cooled Solid Breeder Test Blanket Module Cho, S.; Ahn, M.Y.; Lee, E.S.; Yun, S.; Cho, Nam-Zin; Jung, K.J., ISFNT-8, 2007 |
| Delayed Hopfield-like Neural Network for Solving Inverse Radiation Transport Problems Lee, S.H; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Autumn Meeting, pp.21 - 26, 1996-11 |
| Design Analysis of a Thorium Fueled Reactor with Seed-Blanket Assembly Configuration Cho, Nam-Zin; Lee, K.T, Proc. of the Korean Nuclear Society Spring Meeting, pp.21 - 26, 1997-05 |
| Design Charateristics of Moderation- Enhanced Reactor Core Loaded 100% with MOX Fuel Kim, Y.B; Cho, Nam-Zin, KAIF/KNS Annual Conference, 1996-03 |
| Design Comparisons of TRU Burner Cores with Similar Sodium Void Worth Kim, S.J; Cho, Nam-Zin; Kim, Y.I; Kim, Y.J, International Conference on "Back-End of the Fuel Cycle: From Reseach to Solutions" (GLOBAL 2001), 2001-09 |
| Design of a Medical Reactor Generating High Quality Neutron Beams for BNCT Park, J.H; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Spring Meeting, pp.427 - 432, 1997-05 |
| Determination of Intermediate-Level Performance Criteria for Improvement of Nuclear Power Plant Design and Operation Jung, W.S; Cho, Nam-Zin, International Topical Meeting on Probabilistic Safety Assessment, pp.1366 - 1372, 1993-01 |
| Development of a Three-Dimensional Nodal Diffusion Code Based on the AFEN Methodology Hong, S.G; Cho, Nam-Zin; Noh, J.M., Proc. of the Korean Nuclear Society Spring Meeting, pp.77 - 82, 1995-05 |
| Development of an AFEN Method Code in cylindrical (r,θ,z) Geometry for Design Analysis of Pebble Bed Modular Reactor Cho, Nam-Zin; Lee, J.H; Lee, J.J; Kim, DS, Proc. of the Korean Nuclear Society, 2005-05 |
| Development of Intermediate- Level (Safety Function/System) Performance Criteria Based on Reliability and Risk Models Sung, S.K; Cho, Nam-Zin, Proc. of the Third Inter. Topical Meeting on Nucl. Power Plant Thermal Hydraulics and Operations, v.2, pp.71 - 77, 1988-11 |
| Domain Decomposition Solution of the Neutron Diffusion Equation with an Iterative Parallel Algorithm on a Transputer Network Kim, Y.H; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Autumn Annual Meeting, pp.125 - 130, 1991-10 |
| Effects of Inter-Assembly Spectral Interaction in MOX Cores Analyzed by CASMO-3M/AFEN Cho, Nam-Zin; Jo, C.K., Proc. of the Korean Nuclear Society Spring Meeting, pp.23 - 28, 1994-05 |
| Estimation of Flux Distribution via Observer Design Park, YH; Cho, Nam-Zin, Proc. of the International Conference on the Physics of Reactors:Operation Design and Computation, v.2, pp.59 - 68, 1990-04 |
| Estimation of the Fuel Depletion Code Bias and Uncertainty in Burnup-credit Criticality Analysis Kim, J.W; Cho, Nam-Zin; Lee, S.J; Baeg, C.Y, Proceedings of the Korean Nuclear Society Autumn Meeting, 2006-11 |
| Evaluation of Truncation Error in Minimal Cut Set-Based Fault Tree Analysis Choi, Jong Soo; Cho, Nam-Zin, Proceedings of the Korean Nuclear Society Spring Meeting, 2005-10 |
| Evaluation of U-Zr Hydride Fuel for a Thorium Fuel Cycle in an RTR Concept Lee, K.T; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Spring Meeting, v.1, pp.52 - 57, 1998-05 |
| Extension of AFEN Methodology to Multigroup Problems in Hexagonal-Z Geometry Cho, Nam-Zin; Kim, Y.H; Park, K.W, Proc. of the Korean Nuclear Society Spring Meeting, v.1, pp.137 - 141, 1996-05 |
| Fast Solution of Linear Systems by Wavelet Transform Park, C.J; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Spring Meeting, v.1, pp.282 - 287, 1996-05 |
| Feasibility and Characteristics of Graphite-Filled MOX Fuel Design for Full Loaded PWR Cores Jo, C.K; Cho, Nam-Zin; Kim, Y.H, International Conference on the Physics of Nuclear Science and Technology, pp.495 -, 1998-10 |
| Feasibility Study of Constant Composition TRU Feeding in an Accelerator-Driven Fluid-Fueled Thermal Reactor System Kim, D.S; Cho, Nam-Zin; Park, W.S, International Conference on the Physics of Nuclear Science and Technology, pp.1563 -, 1998-10 |
| Fine-lattice stochastic modeling of particle fuels in an HTGR unit fuel element Yu, H.; Cho, Nam-Zin, 2005 Annual Meeting - American Nuclear Society, v.92, pp.510 - 513, 2005-06-05 |
| FN-Based Nodal Transport Method in X-Y Geometry Hong, S.G; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Autumn Meeting, pp.39 - 44, 1996-11 |
| Fuel Self-Sufficient and Low Proliferation Risk Multi-Recycling of Spent Fuel Cho, Nam-Zin; Hong, S.G; Kim, T.H, The 13th KAIF/KNS Annual Conference, pp.417 -, 1998-04 |
| 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 |
| Generating Nonnegative Multigroup Scattering Cross Sections with Monte Carlo Simulation Kim, Jong Woon; Cho, Nam-Zin, Proc. of the Korean Nuclear Society, 2005-05 |
| 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 |
| 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 |
| 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 |
| 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 |
| 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 |
| 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 |
| 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 |
| 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 |
| 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 |
| 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 |
| 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 |
| 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 |
| 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 |
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Type
- 3 Article
- 5,616 Conference
Date issued
- 546 2020 - 2024
- 2,529 2010 - 2019
- 1,629 2000 - 2009
- 723 1990 - 1999
- 172 1980 - 1989