Browse "Dept. of Nuclear and Quantum Engineering(원자력및양자공학과)" by Author 546

Showing results 184 to 205 of 205

184
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

185
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

186
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

187
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

188
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

189
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

190
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

191
The Nodal Methods in Reactor Core Nuclear Design

Cho, Nam-Zin, Proc. of the Korean Nuclear Society Spring Meeting, pp.45 - 53, 1995-05

192
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

193
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

194
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

195
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

196
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

197
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

198
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

199
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

200
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

201
Waveform Relaxation Method for Reactor Transient Analysis

Park, K.W; Cho, Nam-Zin, KAIF/KNS Annual Conference, 1995-04

202
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

203
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

204
Wavelet-theoretic Method for Solution of Neutron Transport Equation

Cho, Nam-Zin; Liangzhi, Cao, Proceedings of the Korean Nuclear Society Spring Meeting, 2006-05

205
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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