Browse "Dept. of Nuclear and Quantum Engineering(원자력및양자공학과)" by Author 546
Showing results 131 to 190 of 205
| 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 |
| 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 |
| 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 |
| Molecular Dynamics Simulation of Thermomechanical Properties of Mononitride Nuclear Fuel Hong, Qian; Cho, Nam-Zin, Proc. of the Korean Nuclear Society, 2005-05 |
| 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 |
| 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 |
| 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 |
| 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 |
| 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 |
| 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 |
| 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 |
| 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 |
| 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 |
| 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 |
| 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 |
| 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 |
| 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 |
| 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 |
| 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 |
| 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 |
| 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 |
| 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 |
| Optimal Control of Xenon Concentration via Observer Design Woo, H.S; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Annual Meeting, 1989-05 |
| 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 |
| 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 |
| 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 |
| 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 |
| 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 |
| 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 |
| 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 |
| 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 |
| Preconditioners for Krylov Iterative Method for Two-Dimensional MOC Problems Yoo, Han Jong; Cho, Nam-Zin, Proceedings of the Korean Nuclear Society, 2007-10 |
| 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 |
| 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 |
| 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 |
| 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 |
| 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 |
| 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 |
| Reactor Physics in KOREA and Related Topics Cho, Nam-Zin, Proceedings of the Atomic Energy Society of Japan Fall Meeting, 2000-09 |
| 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 |
| 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 |
| 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 |
| 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 |
| 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 |
| 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 |
| Solution of Neutron Diffusion Equation on a Parallel Computer Kim, Y.H; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Spring Annual Meeting, pp.75 - 80, 1991-05 |
| Space-Dependent Feedback Kinetics Calculation in the Anayltic Function Expansion Nodal Method Kim, D.S; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Spring Meeting, 2000-05 |
| SPANDOM - Source Projection Analytic Nodal Discrete Ordinates Method Kim, T.H; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Autumn Meeting, pp.111 - 116, 1994-10 |
| Stability Analysis of an Accelerator Driven Fluid-Fueled Subcritical Reactor System Cho, Nam-Zin; Kim, D.S, Proc. of the Korean Nuclear Society Spring Meeting, pp.90 - 95, 1997-05 |
| Stability Analysis of An Accelerator-Deiven Subcritical Fluid-Fueled Reactor System for Radioactive Waste Transmutation Kim, D.S; Cho, Nam-Zin, Internation Conference on Future Nuclar Systejms, v.2, pp.1393 -, 1997-10 |
| Studies on Burnup Credit Criticality Safety for Storage and Transportation of PWR Spent Fuel in Korea Koh, D.J; Cho, Nam-Zin, The Sixth International Conference on Nuclear Criticality Safety (ICNT'99), v.3, pp.1934 -, 1999-09 |
| Sub-fine Lattice Stochastic Modeling of Randomly Distributed Particle Fuels with Variability in Packing Fraction Cho, Nam-Zin; Yu, Hui, Proceedings of the Koarean Nuclear Society Autumn Meeting, 2006-11 |
| Supercomputing with Parallel Computers in Reactor Analysis Cho, Nam-Zin; Kim, Y.H; Song, J.S, Proc. of the 7th KAIF/KNS Annual Conference, pp.465 - 472, 1992-04 |
| Temperature distributions in a pebble with dispersed fuel particles calculated by Monte Carlo method Song, J.H.; Cho, Nam-Zin, 2008 Annual Meeting on American Nuclear Society, pp.443 - 445, 2008-06-08 |
| The Additive Angular Rebalance Acceleration Method for Solving Neutron Transport Equations in X-Y Geometry Park, C.J; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Spring Meeting, 2001-05 |
| The AFEN Method in Cylindrical (r,θ,z) Geometry for Pebble Bed Reactors - Extension to Treatment of Void Regions - Lee, Jaejun; Lee, Gil Soo; Cho, Nam-Zin, Proceedings of the Korean Nuclear Society Spring Meeting, pp.553 -, 2006-10 |
| The AFEN Method in Cylindrical (r,θ,z) Geometry for Pebble Bed Reactors - Incorporation of Acceleration and Discontinuity Factor Lee, Jaejun; Cho, Nam-Zin, Proceedings of the Korean Nuclear Society, 2007-10 |
| The Method of Characteristics Neutron Transport Calculations Accelerated by Coarse-Mesh Angular Dependent Rebalance Park, Young Ryong; Cho, Nam-Zin, SIAM Conference on Computational Science & Engineering, 2005-02 |
| The Method of Streaming Rays for Neutron Transport Problems Cho, Nam-Zin; Hong, S.K., Proc. of the Korean Nuclear Society Spring Meeting, pp.67 - 72, 1994-05 |
| The MOC Neutron Transport Calculations Accelerated by Coarse-mesh Angular Dependent Rebalance Park, Young Ryong; Cho, Nam-Zin, Proc. of the Korean Nuclear Society, pp.81 - 82, 2004-10 |
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