Browse "Dept. of Nuclear and Quantum Engineering(원자력및양자공학과)" by Author 546
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| 2-D and 3-D Whole-Core Transport Calculations of the OECD Benchmark Problem c5G7 MOX by CRX Cho, Nam-Zin; Lee, G.S; Park, C.J, International Conference on the New Frontiers of Nuclear Technology: Reactor Physics, Safety and High-Performance Computing PHYSOR 2002, 2002-10 |
| 3-D Whole-Core Transport Calculations of the Extended OECD Benchmark Problem C5G7 MOX by the CRX Code Lee, G.S.; Cho, Nam-Zin, International Conference on Nuclear Technology: Achieving Global Economic Growth While Safeguarding the Environment, v.89, pp.271 -, 2003-11-16 |
| A Compute Code for Common-Cause Failure Analysis Park, B.H; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Spring Annual Meeting, pp.341 - 346, 1991-05 |
| A Markovian Analysis of Limiting Conditions of Operation for the Reactor Protection System Papazoglou, I.A; Cho, Nam-Zin, Proc. of the International ANS/ENS Topical Meeting on Probabilistic Safety Methods and Applications, v.1, pp.1 - 8, 1985-02 |
| A Benchmark of Beowulf Cluster for Nuclear Engineering Advanced Computation Park, J.H; Cho, Nam-Zin; Kim, M.S, Proc. of the Korean Nuclear Society Spring Meeting, v.1, pp.7 -, 1999 |
| A Comparative Design Analysis of Transuranic Burner Cores with Low Sodium Void Reactivity Kim, S.J; Cho, Nam-Zin; Kim, Y.J, Advances in Reactor Physics and Mathematics and Computation into the Next Millennium (PHYSOR 2000), pp.IX.C.-1 -, 2000-05 |
| A Comparison of Two Nodal Codes: Avanced Nodal Code (ANC) and Analytic Function Expansion Nodal (AFEN) Code Cho, Nam-Zin, Proc. of the International Conference on the Physics of Reactors:Operation, Design and Computation, 1996-09 |
| A Decision-Theoretic Methodology for Reliability and Risk Allocation in Nuclear Power Plant Cho, Nam-Zin; Papazoglou, I.A; Bari, R.A; El-Bassioni, A, Proc. of the International ANS/ENS Topical Meeting on Probabilistic Safety Methods and Applications, v.1, pp.1 - 10, 1985-02 |
| A Flux- and Adjoint Flux-Weighting Method for the Control Rod Cusping Problem in Nodal Methods Kim, Y.H; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Spring Annual Meeting, 1990-05 |
| A Fusion Technique of 2-D/1-D Methods for Three-Dimensional Whole-Core Transport Calculations Cho, Nam-Zin; Lee, G.S; Park, C.J, Proc. of the Korean Nuclear Society, 2002-05 |
| A Hofield-Like Neural Network with Random Updating Intervals for Solving Inverse Radiation Transport Problems Lee, S.H; Cho, Nam-Zin, Joint International Conference on Mathematical Methods and Supercomputing for Nuclear Applications, pp.1245 -, 1997-10 |
| A Linear Multiple Balance Method for Discrete Ordinates Neutron Transport Equations Park, C.J.; Cho, Nam-Zin, Proc. of the Korean Nuclear Society, 2000-10 |
| A Lyapunov Function-Free Method for Stability Domains of Nonlinear Reactors Yang, C.Y; Cho, Nam-Zin, Proc. of the 1992 Topical Meeting on Advances in Reactor Physics, v.2, pp.433 - 444, 1992-03 |
| A Modified Generalized Equivalence Theory for Homogenization of the Assembly and Baffle-Reflector Cheng, H.W; Cho, Nam-Zin, Proc. of the International Conference on the Physics of Reactors:Operation, Design and Computation70, 1996-09 |
| A Multigroup Diffusion Nodal Scheme : Hybrid of AFEN and PEN Methods Cho, Nam-Zin; Noh, J.M., Proc. of the Korean Nuclear Society Autumn Meeting, pp.29 - 34, 1995-10 |
| A Multigroup Diffusion Nodal Scheme in Rectangular and Hexagonal Geometries: Hybrid of AFEN and PEN Methods Noh, J.M; Cho, Nam-Zin, Proc. of the International Conference on the Physics of Reactors:Operation, Design and Computation50, 1996-09 |
| A New Acceleration Method of Additive Dependnet Rebalance with Extrapolation for Discrete Ordinates Transport Equation Park, C.J.; Cho, Nam-Zin, Proc. of the Korean Nuclear Society, 2001-10 |
| A New Approach to Effective Thermal Conductivity for VHTR Fuels Nam Zin Cho; Hui, Yu, Proceedings of the Korean Nuclear Society, 2007-05 |
| A New Approach to Solving Neutron Diffusion Equation Based on Wavelet Theory Park, C.J; Cho, Nam-Zin, International Conference on the Mathematics and Computations, Reactor Physics, and Environmental Analyses, v.2, pp.1445 - 1454, Proceedings of the International Conference on Mathematics and Computations, Reactor Physics, and Environmental Analyses, 1995-04 |
| A New Approach to Treating Baffle/Reflector Heterogenity in AFEN Methology Cho, Nam-Zin; Kim, D.S; Kim, Y.H, Proc. of the Korean Nuclear Society Spring Meeting, v.1, pp.148 - 153, 1996-05 |
| A New Method for Reconstructing Pointwise Flux Distribution Based on Maximum Entropy Principle Jung, W.S; Cho, Nam-Zin, Proc. of the International Conference on the Physics of Reactors:Operation, Design and Computation, v.2, pp.1 - 10, 1990-04 |
| A New Nodal Method : Approach of Analytic Basis Function Expansion Noh, J.M; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Spring Meeting, pp.13 - 18, 1993-05 |
| A Preliminary Study of Burnup Credit Applied to Criticality Analysis of Spent Fuels Kim, Jong Woon; Cho, Nam-Zin; Jang, Hyun-Kie; Choi, Byung-Il; Lee, Heung-Young, Proceedings of International Symposium on Radiation Safety Management (ISRSM 2005), pp.506 - 517, 2005-11 |
| A Proposed Concept of Passive Pressurized Water Reactor Based on Existing Reactor Coolant System Design Chang, S.H; Baek, W.P; Lee, S.W; No, H.C; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Autumn Meeting, pp.431 - 436, 1992-10 |
| A Rapidly Convergent Generalized Rebalance Method (GRM) for Discrete Ordinates Transport Equations Hong, S.G; Cho, Nam-Zin; Kim, K.S; Song, J.S, Proceedings of the Korean Nuclear Society Spring Meeting, 2007-05 |
| A Rebalance Nonlinear Iteration Method for Solving the Neutron Transport Equations Hong, S.G; Cho, Nam-Zin, Proc. of the International Conference on the Physics of Reactors:Operation, Design and Computation376, 1996-09 |
| A Refinement of the Analytic Function Expansion Nodal Method with Interface Flux Moments Woo, S.W; Cho, Nam-Zin; Noh, J.M, Proc. of the Korean Nuclear Society Spring Meeting, v.1, pp.17 -, 1999 |
| A Refinement of the Analytic Function Expansion Nodal Method with Transverse Gradient Basis Functions and Interface Flux Moments Woo, S.W; Cho, Nam-Zin; Noh, J.M, Advances in Reactor Physics and Mathematics and Computation into the Next Millennium (PHYSOR 2000), pp.IX.F.-2 -, 2000-05 |
| A Spectral Analytic Discrete- Ordinates Transport Method Based on Infinite Medium Green's Function for Multiplying Fission Source Problems Jung, D.H; Cho, Nam-Zin, Proc. of the Korean Nuclear Society, 2001-10 |
| A Spectral Form Function Method for Reconstructing Pointwise Flux Distributions Jeong, H.Y; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Annual Meeting, 1988-05 |
| A Spectral-Galerkin Nodal Method for Solving the Two-Dimensional Multigroup Diffusion Equations Cheng, H.W; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Spring Meeting, v.1, pp.157 - 162, 1996-05 |
| A Spectrum Correction Method for Fuel Assembly Rehomogenization Lee, Kyung Taek; Cho, Nam-Zin, Proc. of the Korean Nuclear Society, 2004-05 |
| A Study on the Signal Processing of the Senstivity Depletion Laws for Rhodium Self-Powered Neutron Detectors (SPNDs) Kim, G.G; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Spring Meeting, v.1, pp.17 -, 1999 |
| A Superelement-Sweeping Method for Neutron Transport Calculations in Heterogeneous Geometry Lee, G.S; Cho, Nam-Zin, Proc. of the Korean Nuclear Society, 2003-10 |
| A Transition Cycle Strategy to Enhance Minor Actinide Burning Potential in the Pan-Shape LMR Core Kim, S.J; Kim, Y.I; Kim, Y.J; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Spring Meeting, 2001-05 |
| Acceleration and Parallelization of the Method of Characteristics for Lattice and Whole-Core Heterogeneous Calculations Lee, G.S; Cho, Nam-Zin; Hong, S.G, Advances in Reactor Physics and Mathematics and Computation into the Next Millennium (PHYSOR 2000), pp.II.C-1 -, 2000-05 |
| Acceleration of the AFEN Method by Two-Node Nonlinear Iteration Moon, K.S; Cho, Nam-Zin; Noh, J.M; Hong, S.G, Proc. of the Korean Nuclear Society Spring Meeting, pp.87 - 92, 1998-05 |
| Acceleration of the Method of Characteristics in the CRX Lattice Calculation Code for Anisotropic Scattering Problems Lee, G.S; Cho, Nam-Zin; Hong, S.G, Proc. of the Korean Nuclar Society Autumn Meeting, pp.49 -, 1999-10 |
| Acceleration of Three-Dimensional AFEN Nodal Codes via Coarse Group Rebalance and Direct Matrix Inverse Kim, D.S; Cho, Nam-Zin, Mathematics and Computation, Reactor Physics and Environmental Analysis in Nuclear Applications (M&C'99), pp.168 -, 1999-09 |
| Accident Sequence Quantification of Phased Mission Systems Using Markov Approach Jung, W.S; Cho, Nam-Zin, International Conference on Design and Safety of Advanced Nuclear Power Plants, pp.1 - 6, 1992-10 |
| Additive Angular Dependent Acceleration Method of the Discrete Ordinates Transport Calculations Park, C.J.; Cho, Nam-Zin, ANS International Meeting on Mathematical Method for Nuclear Applications (M&C 2001), 2001-09 |
| Adomian Decomposition Method for the Reactor Point Kinetics Cho, Y.C; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Spring Meeting, pp.67 - 72, 1992-05 |
| AFENX: A Reactor Core Analysis Code Based on Analytic Function Expansion Nodal Method Cho, Nam-Zin; Kim, D.S, International Conference on the New Frontiers of Nuclear Technology: Reactor Physics, Safety and High-Performance Computing PHYSOR 2002, 2002-10 |
| An Analytic Relations Method for the Calculation of Actinides Concentrations Chang, D.I; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Spring Annual Meeting, pp.499 - 504, 1991-05 |
| An Adjoint p-CMFD Scheme for Monte Carlo k-Eigenvalue Calculations Cho, Nam-Zin; Yun, S.H; Lee, K.T; Lee, G.S, Proc. of the Korean Nuclear Society, 2004-05 |
| An approach of super-element sweeping for the solution of neutron transport equation in heterogeneous geometry Lee, G.S.; Cho, Nam-Zin, PHYSOR 2004: The Physics of Fuel Cycles and Advanced Nuclear Systems - Global Developments, pp.1855 - 1864, 2004-04-25 |
| An efficient Algorithm for Complexity Measures of Large Systems Based on the Dsijoint Set Method Jung, W.S; Cho, Nam-Zin, International Conference on Probabilistic Safety Assessment Methodology and Application, 1996-06 |
| An Efficient Multigrid Algorithm for the Reactor Eigenvalue Problems Cho, Nam-Zin; Lee, K.H; Kim, Y.H, Proc. of the Korean Nuclear Society Spring Meeting, pp.27 - 32, 1997-05 |
| An Evaluation of the Deployment of Moderation-Enhanced MOX Fuel Fully Loaded in Pressurized Water Reactor Kim, Y.B; Cho, Nam-Zin, Proc. of the International Conference on the Physics of Reactors:Operation, Design and Computation57, 1996-09 |
| An Expansion Method for Determining Asymptotic Stability Domains of Nonlinear Reactors Yang, C.Y; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Spring Meeting, pp.447 - 452, 1992-05 |
| An extension of the generation method of non-negative scattering cross-sections for a two dimensional geometry Kim, J.W.; Lee, Y.-O.; Cho, Nam-Zin, International Conference on Mathematics, Computational Methods and Reactor Physics 2009, M and C 2009, v.5, pp.3254 - 3266, 2009-05-03 |
| An Improved Maximum Entropy Method for the Reconstruction Problem in Nodal Calculation Jung, W.S; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Annual Meeting, 1989-10 |
| An Improved Monte Carlo Method Applied to Heat Conduction Problem of a Fuel Pebble Song, Jae Hoon; Cho, Nam-Zin, Proceedings of the Korean Nuclear Society, 2007-10 |
| An Improved Monte Carlo Method for Solving Heat Conduction Problems with Complex Geometry Song, Jae Hoon; Cho, Nam-Zin, Proceedings of the Korean Nuclear Society Spring Meeting, 2007-05 |
| An Observer-Theoretic Approach to Estimating Neutron Flux Distribution Park, Y.H; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Annual Meeting, 1989-10 |
| An Optimal Fuel Management Method Based on CANDU In-Core Detector Readings Jeong, C.J; Choi, H.B; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Spring Meeting, 2001-05 |
| An Optimization Study of Gadolinia Burnable Absorber Design for Westinghouse Type 16×16 Fuel Assembly Lee, G.S; Lee, K.T; Cho, Nam-Zin; Kim, Y.H; Jeon, K.L, Proc. of the Korean Nuclear Society, pp.123 - 124, 2004-10 |
| Analysis of the Nuclear Subcriticality for the High Density Spent Fuel Storage at PWR Plants Koh, D.J; Jo. C.K; Ryu, H.G; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Spring Meeting, pp.470 - 475, 1998-05 |
| Analysis of VHTR Fuel Compact Cell Using Fine-Lattice Stochastic Modeling Cho, Nam-Zin; Hui, Yu, Proc. of the Korean Nuclear Society, 2005-05 |
| Analytic Function Expansion Nodal Method for Hexagonal Nodes Noh, J.M; Cho, Nam-Zin, 1994 Topical Meeting on Advances in Reactor Physics, 1994-04 |
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- 911 Thesis(Master)
- 546 Thesis(Ph.D)
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- 1,203 2020 - 2024
- 4,359 2010 - 2019
- 2,657 2000 - 2009
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