Browse "Dept. of Nuclear and Quantum Engineering(원자력및양자공학과)" by Author 546
Showing results 167 to 205 of 205
| 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 |
| The Nodal Methods in Reactor Core Nuclear Design Cho, Nam-Zin, Proc. of the Korean Nuclear Society Spring Meeting, pp.45 - 53, 1995-05 |
| The p-version of the Finite Element Method and Domain Decomposition Approach for Two-Dimensional Diffusion Equations Park, KW; Cho, Nam-Zin, Proc. of the Korean Nuclear Society, 2000-10 |
| The Use of Burnup Credit in Criticality Control for the Korean Spent Fuel Management Program Koh, D.J; Jo, C.K; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Autumn Meeting, pp.245 - 250, 1997 |
| Thermal feedback transient analysis of a pebble fuel based on the two-temperature homogenized model Yu, H.; Kim, J.W.; Cho, Nam-Zin, 2008 Winter Meeting and Nuclear Technology Expo: Nuclear Power-Ready, Steady, Go, pp.677 - 679, 2008-11-09 |
| Three-Dimensional Whole-Core Transport Calculation of the OECD Benchma가 Problem C5G7 MOX by The CRX Code Lee, Gil Soo; Cho, Nam-Zin, Nuclear Mathematical and Computational Science M&C 2005, 2005-09 |
| TOPS nodal code solutions for the OECD/PBMR-400 benchmark problem Lee, J.; Lee, J.H.; Yoo, H.J.; Lee, G.S.; Cho, Nam-Zin, PHYSOR-2006 - American Nuclear Society's Topical Meeting on Reactor Physics, 2006-09-10 |
| Transition Cycle Behavior of the Pan-Shape Transuranic Burner Core with Low Sodium Void Reactivity Kim, S.J; Cho, Nam-Zin; Kim, Y.J, Eighth International Conference on Nuclear Engineering, 2000-04 |
| Two-Node Nonlinear Iterative AFEN Method in Three-Dimensional Geometry Kim, D.S; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Autumn Meeting, v.1, pp.49 -, 1998 |
| Variance Reduction Techniques for Uncertainty Analysis of Fault Trees Choi, J.S; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Spring Annual Meeting, 1990-05 |
| Verification of the Analytic Function Expansion Nodal (AFEN) Method in Cylindrical (r,θ,z) Geometry for Pebble Bed Reactors Cho, Nam-Zin; Lee, J.H; Lee, J.J; Kim, DS, Proceedings of the Korean Nuclear Society Autumn Meeting, 2005-10 |
| Waveform Relaxation Method for Reactor Transient Analysis Park, K.W; Cho, Nam-Zin, KAIF/KNS Annual Conference, 1995-04 |
| Wavelet Theory for Solution of the Neutron Diffusion Equation Park, C.J; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Annual Meeting, pp.79 - 84, 1994-10 |
| Wavelet-Based Image Reconstruction in Transmission Computed Tomography Cho, Nam-Zin; Park, C.J; Park, J.W, ANS Radiation Protection and Shielding Division Topical Conference, pp.141 -, 1998-04 |
| Wavelet-theoretic Method for Solution of Neutron Transport Equation Cho, Nam-Zin; Liangzhi, Cao, Proceedings of the Korean Nuclear Society Spring Meeting, 2006-05 |
| Whole-Core Heterogeneous Transport Calculations and Their Comparison with Diffusion Results Lee, G.S; Cho, Nam-Zin; Hong, S.G, Proc. of the Korean Nuclear Society Spring Meeting, 2000-05 |
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Type
- 2,789 Article
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- 430 Patent
- 911 Thesis(Master)
- 546 Thesis(Ph.D)
Open Access
- 152 OA Article
Date issued
- 1,223 2020 - 2024
- 4,359 2010 - 2019
- 2,657 2000 - 2009
- 1,431 1990 - 1999
- 449 1980 - 1989