**International &
Domestic Conference Papers **

**[International Conference Papers]**** **

1. Cho, N.Z., Papazoglou, I.A., Bari, R.A., and El-Bassioni, A., "A Decision-Theoretic Methodology for Reliability and Risk Allocation in Nuclear Power Plants, Proceedings of the International ANS/ENS Topical Meeting on Probabilistic Safety Methods and Applications, Volume 1, pp.14-1 to 14-10, February 1985, San Francisco, California.

2. Papazoglou, I.A., Cho, N.Z., "A Markovian Analysis of Limiting Conditions of Operation for the Reactor Protection System," Proceedings of the International ANS/ENS Topical Meeting on Probabilistic Safety Methods and Applications, Volume 1, pp. 36-1 to 36-8, February 1985, San Francisco, California.

3. Bari, R.A., Cho, N.Z., and Papazoglou, I.A., "Reliability Allocation in Nuclear Power Plants," Transaction of the 8th International Conference on Structural Mechanics in Reactor Technology, August 1985, Brussels, Belgium.

4. Cho, N.Z., Bozoki, G.E., and Youngblood, R.W., "Comparison of Methods Applicable to Evaluation of Nuclear Power Plant Technical Specifications," Proceedings of the International ANS/ENS Topical Engineering on Thermal Reactor Safety, Volume 2, pp.XII.2-1 to XII.2-8, February 1986, San Diego, California.

5. Youngblood, R., Xue, D., and Cho, N.Z., "Pair Importance Measures in Systems Analysis," Proceedings of the International ANS/ENS Topical Meeting on Thermal Reactor Safety, Volume 2, pp.X.8-1 to X.8-7, February 1986, San Diego, California.

6. Yang, C.Y., Cho, N.Z., "Power Distributions in a Nuclear Reactor Core Under Various Operating Conditions and Their Safety Implications," Proceedings of the International ENS/ANS Conference on Thermal Reactor Safety, Vol.4, pp.1314-1323, October 1988, Avignon, France.

7. Sung, S.K., Cho, N.Z., "Development of Intermediate- Level (Safety Function/System) Performance Criteria Based on Reliability and Risk Models, Proceedings of the Third International Topical Meeting on Nuclear Power Plant Thermal Hydraulics and Operations, Vol.2, pp. B11.71-B11.77, November 1988, Seoul, Korea.

8. Park, Y.H., Cho, N.Z., "Estimation of Flux Distribution via Observer Design," Proceedings of the International Conference on the Physics of Reactors : Operation, Design and Computation, Vol.2, pp. XIII.59-XIII.68, April 1990, Marseille, France.

9. Jung, W.S., Cho, N.Z., "A New Method for Reconstructing Pointwise Flux Distribution Based on Maximum Entropy Principle," Proceedings of the International Conference on the Physics of Reactors : Operation, Design and Computation, Vol.2, pp. VIII.1 - VIII.10, April 1990, Marseille, France.

10. Lee, J.T., Lee, B.H., Cho, N.Z., and Oh, S.K., "A Cell Homogenization Method for Strongly Heterogeneous Research Reactors," Proceedings of the International Topical Meeting on Advances in Mathematics, Computations, and Reactor Physics, Vol.3, pp.15.2.3.1-12, April 1991, Pittsburgh, U.S.A.

11. Jung, W.S., Cho, N.Z., "Reconstruction of Pointwise Neutron Flux Distribution via Minimum Cross-Entropy Principle," Proceedings of the International Topical Meeting on Advances in Mathematics, Computation, and Reactor Physics, Vol.3, pp.15.1.2.1-12, April 1991, Pittsburgh, U.S.A.

12. Yang, C.Y., Cho, N.Z., "A Lyapunov Function-Free Method for Stability Domains of Nonlinear Reactors," Proceedings of the 1992 Topical Meeting on Advances in Reactor Physics, Vol.2, pp.2.433-2.444, March 1992, Charleston, U.S.A.

13. Cho, N.Z., Song, J.S., "Implementation of a Parallel Algorithm in 2-D Assembly Transport Calculation on a Transputer," Proceedings of the International Symposium on Numerical Transport Theory, pp.72-75, May 1992, Moscow, Russia.

14. Jung, W.S., Cho, N.Z., "Accident Sequence Quantification of Phased Mission Systems Using Markov Approach," International Conference on Design and Safety of Advanced Nuclear Power Plants, Vol.IV, pp.P16.1-1 to 6, October 1992, Tokyo, Japan.

15. Cho, N.Z., Jung, W.S., "Probabilistic Safety Criteria (PSC) Allocation for Optimum Design and Operation of a Nuclear Power Plant," Proceedings of the First Korea/Japan Joint Workshop on Probabilistic Safety Assessment (PSA), November 1992, Seoul, Korea.

16. Jung, W.S., Cho, N.Z., "Determination of Intermediate-Level Performance Criteria for Improvement of Nuclear Power Plant Design and Operation," International Topical Meeting on Probabilistic Safety Assessment, pp.1366-1372, January 1993, Clearwater Beach, Florida, U.S.A.

17. Kim, Y.H., Cho, N.Z., "Parallel Schwarz Algorithm for the Neutron Diffusion Equation on an MIMD Architecture," International Conference on Mathematical Methods and Supercomputing in Nuclear Applications, Vol.2, pp.100-111, April 1993, Karlsruhe, FRG.

18. Park, M.G., Cho, N.Z., "Online Self-Tuning Control of Korea Multipurpose Research Reactor Based on Gaussian Function Neural Network," Proceedings of Fourth Asian Symposium on Research Reactors, pp.157-166, November 1993, Beijing, China.

19. Cho, N.Z., Jo, C.K., "Neutron Transport Assembly Calculation with Non-Zero Net Current Boundary Condition for Group Constant Generation," International Conference on Reactor Physics and Reactor Computations, January 1994, Tel Aviv, Israel.

20. Noh, J.M., Cho, N.Z., "Analytic Function Expansion Nodal Method for Hexagonal Nodes," 1994 Topical Meeting on Advances in Reactor Physics, April 1994, Knoxville, U.S.A..

21. Noh, J.M., Cho, N.Z., "Intranodal Burnup Gradient Correction in Analytic Function Expansion Nodal (AFEN) Method," Proceedings of the International Conference on Mathematics and Computations, Reactor Physics, and Environmental Analyses, Vol.2, pp.1435-1444, April 1995, Portland, U.S.A.

22. Park, C.J., Cho, N.Z., "A New Approach to Solving Neutron Diffusion Equation Based on Wavelet Theory," Proceedings of the International Conference on Mathematics and Computations, Reactor Physics, and Environmental Analyses, Vol.2, pp.1445-1454, April 1995, Portland, U.S.A.

23. Jung, W.S., Cho, N.Z., "An efficient Algorithm for Complexity Measures of Large Systems Based on the Dsijoint Set Method," International Conference on Probabilistic Safety Assessment and Management, June 1996, Crete, Greece.

24. Cho, N.Z., "Nuclear Energy Policy and R&D Prospects: The Korean Case," (invited), International Conference on the Physics of Reactors, Vol. 1, p.O-21, September 1996, Mito, Japan.

25. Noh, J.M., Cho, N.Z., "A Multigroup Diffusion Nodal Scheme in Rectangular and Hexagonal Geometries: Hybrid of AFEN and PEN Methods," International Conference on the Physics of Reactors Vol. 1, p.A-50, September 1996, Mito, Japan.

26. Cheng, H.W., Cho, N.Z., "A Modified Generalized Equivalence Theory for Homogenization of the Assembly and Baffle-Reflector," International Conference on the Physics of Reactors, Vol. 1, p.A-80, September 1996, Mito, Japan.

27. Cho, N.Z., Hong, S.G., "CRX: A Transport Code for Cell and Assembly Calculations Based on Characteristic Method," International Conference on the Physics of Reactors, Vol. 1, p.A-250, September 1996, Mito, Japan.

28. Cho, N.Z., et al., "A Comparison of Two Nodal Codes: Avanced Nodal Code (ANC) and Analytic Function Expansion Nodal (AFEN) Code," International Conference on the Physics of Reactors, Vol. 1, p.A-288, September 1996, Mito, Japan.

29. Hong, S.G., Cho, N.Z., "A Rebalance Nonlinear Iteration Method for Solving the Neutron Transport Equations," International Conference on the Physics of Reactors, Vol. 1, p.A-376, September 1996, Mito, Japan.

30. Kim, Y.B., Cho, N.Z., "An Evaluation of the Deployment of Moderation-Enhanced MOX Fuel Fully Loaded in Pressurized Water Reactor," International Conference on the Physics of Reactors, Vol. 2, p.D-57, September 1996, Mito, Japan.

31. Cho, N.Z., "Policies and Technology Development For the Nuclear Fuel Cycle in Korea," College of Engineering Industrial Liaison Program 19th Annual Conference, p.21, March 1997, Berkeley, U.S.A..

32. Kim, D.S., Cho, N.Z., "Stability Analysis of An Accelerator - Driven Subcritical Fluid-Fueled Reactor System for Radioactive Waste Transmutation," International Conference on Future Nuclear Systems, Vol. 2, p.1393, October 1997, Yokohama, Japan.

33. Lee, S.H., Cho, N.Z., "A Hofield-Like Neural Network with Random Updating Intervals for Solving Inverse Radiation Transport Problems," Joint International Conference on Mathematical Methods and Supercomputing for Nuclear Applications, Vol. 2, p.1245, October 1997, Saratoga, U.S.A..

34. Cho, N.Z., Park, C.J., Park, J.W., "Wavelet-Based Image Reconstruction in Transmission Computed Tomography," (invited), ANS Radiation Protection and Shielding Division Topical Conference, Vol. 1, p.141, April 1998, Nashville, U.S.A.

35. E. Greenspan, Cho, N.Z., Hong, S.G., Kim, T.H., W.E. Kastenberg, "Multi-Recycleing of Spent Fuel with Low Proliferation Risk," International Conference on Emerging Nuclear Energy System, June 1998, Tel-Aviv, Israel.

36. Jo, C.K., Cho, N.Z., and Kim, Y.H., "Feasibility and Characteristics of Graphite-Filled MOX Fuel Design for Full Loaded PWR Cores," International Conference on the Physics of Nuclear Science and Technology, Vol 1, p.495, October 1998, Long Island, U.S.A.

37. Kim, D.S., Cho, N.Z., and Park, W.S., "Feasibility Study of Constant Composition TRU Feeding in an Accelerator-Driven Fluid-Fueled Thermal Reactor System," International Conference on the Physics of Nuclear Science and Technology, Vol 2, p.1563, October 1998, Long Island, U.S.A.

38. Park, C.J., Cho, N.Z., "Image Reconstruction in Emission Computed Tomography via Multigrid Wavelet-Based Natural Pixel Method," International Conference on the Physics of Nuclear Science and Technology, Vol 2, p.1703, October 1998, Long Island, U.S.A.

39. Seo, C.G., Park, C.J., Cho, N.Z., and Kim, H.R., "Pin Power Reconstruction of HANARO Fuel Assembly via Gamma Scanning," The Sixth World Conference on Neutron Radiography, p.41, May 1999, Osaka, Japan.

40. Koh, D.J., Cho, N.Z., "Studies on Burnup Credit Criticality Safety for Storage and Transportation of PWR Spent Fuel in Korea," The Sixth International Conference on Nuclear Criticality Safety(ICNC '99), Vol 3, p.1394, September, Versailles, France.

41. Hong, S.G., Cho, N.Z., "Angular Dependent Rebalance (ADR) Iteration for Discrete-Ordinates Transport Problems in Equilateral Triangular Meshes," Mathematics and Computation, Reactor Physics and Environmental Analysis in Nuclear Applications (M&C '99), Vol 1, p.74, September 1999, Madrid, Spain.

42. Kim, D.S., Cho, N.Z., "Acceleration of Three-Dimensional AFEN Nodal Codes via Coarse Group Rebalance and Direct Matrix Inverse," Mathematics and Computation, Reactor Physics and Environmental Analysis in Nuclear Applications (M&C '99), Vol 1, p. 168, September 1999, Madrid, Spain.

43. Park, J.H., Cho, N.Z., and Kim, J., "Neutronic Analysis of the KSTAR Tokamak Using Beowulf Cluster," Ninth International Conference on Radiation Shileding (ICRS-9), C2-16, October 1999, Tsukuba, Japan.

44. Kim, S.J., Cho, N.Z., and Kim, Y.J., "Transition Cycle Behavior of the Pan-Shape Transuranic Burner Core with Low Sodium Void Reactivity," Eighth International Conference on Nuclear Engineering (ICON-8), April 2000, Boltimore, U.S.A.

45. Lee, G.S., Cho, N.Z., and Hong, S.G., "Acceleration and Parallelization of the Method of Characteristics for Lattice and Whole-Core Heterogeneous Calculations," Advances in Reactor Physics and Mathematics and Computation into the Next Millennium (PHYSOR 2000), II.C.-1, May 2000, Pittsburgh, U.S.A.

46. Kim, S.J., Cho, N.Z., and Kim, Y.J., "A Comparative Design Analysis of Transuranic Burner Cores with Low Sodium Void Reactivity," Advances in Reactor Physics and Mathematics and Computation into the Next Millennium (PHYSOR 2000), III.B.-3, May 2000, Pittsburgh, U.S.A.

47. Ahn, J.G., Cho, N.Z., et al., "Comparison of Criticality Benchmark Calculations on the UO2 and MOX Fuel Arrays Using ENDF/B-V and ENDF/B-VI Data," Advances in Reactor Physics and Mathematics and Computation into the Next Millennium (PHYSOR 2000), IX.C.-1, May 2000, Pittsburgh, U.S.A.

48. Woo, S.W., Cho, N.Z., and Noh, J.M., "A Refinement of the Analytic Function Expansion Nodal Method with Transverse Gradient Basis Functions and Interface Flux Moments," Advances in Reactor Physics and Mathematics and Computation into the Next Millennium (PHYSOR 2000), IX.F.-2, May 2000, Pittsburgh, U.S.A.

49. Cho, N.Z., "Reactor Physics and Nuclear Engineering Education in Korea," Advances in Reactor Physics and Mathematics and Computation into the Next Millennium (PHYSOR 2000), XIV.A.-7, May 2000, Pittsburgh, U.S.A.

50. Cho, N.Z., "Reactor Physics in KOREA and Related Topics," Proceedings of the Atomic Energy Society of Japan Fall Meeting, September 2000, Aomori, Japan.

51. Park, C.J., Cho, N.Z., "Additive Angular Dependent Acceleration Method of the Discrete Ordinates Transport Calculations," ANS International Meeting on Mathematical Methods for Nuclear Applications (M&C 2001), XIV.A.-7, September 2001, Salt Lake City, U.S.A. (CD-ROM)

52. Noh, J.M., Joo, H.K., Yoo, J.W., and Cho, N.Z., "One-Dimensional Heterogeneous Interface Model for Inter-Assembly Thermal Flux Gradient Correction of Homogenization Parameters," ANS International Meeting on Mathematical Methods for Nuclear Applications (M&C 2001), XIV.A.-7, September 2001, Salt Lake City, U.S.A. (CD-ROM)

53. Sang Ji Kim, Cho, N.Z., Young Il Kim, Young Jin Kim, "Design Comparisons of TRU Burner Cores with Similar Sodium Void Worth", International Conference on "Back-End of the Fuel Cycle: From Reseach to Solutions" (GLOBAL 2001), September 2001, Paris, France (CD-ROM)

54. Cho, N.Z., "Neutronic Design Approach to a Small Medical Reactor for BNCT," Proceedings of the 2000 Workshop on the Utilization of Research Reactors, p. 368, November 20-24, 2000, Taejon, Korea, JAERI-Conf 2001-017.

55. Do Sam Kim, and Cho, N.Z., "Comparative Analysis of Static and Kinetic Calculational Features in the Analytic Function Expansion Nodal Method", International Conference on the New Frontiers of Nuclear Technology : Reactor Physics, Safety and High-Performance Computing PHYSOR 2002, October 2002, Seoul, Korea (CD-ROM)

56. Cho, N.Z., Lee, G.S., and Chang Je Park , "2-D and 3-D Whole-Core Transport Calculations of the OECD Benchmark Problem C5G7 MOX by CRX", International Conference on the New Frontiers of Nuclear Technology : Reactor Physics, Safety and High-Performance Computing PHYSOR 2002, October 2002, Seoul, Korea (CD-ROM)

57. Cho, N.Z., and Do Sam Kim, "AFENX: A Reactor Core Analysis Code Based on Analytic Function Expansion Nodal Method", International Conference on the New Frontiers of Nuclear Technology : Reactor Physics, Safety and High-Performance Computing PHYSOR 2002, October 2002, Seoul, Korea (CD-ROM)

58. Cho, N.Z., Lee, G.S., and Chang Je Park, "On a New Acceleration Method for 3D Whole-Core Transport Calculations", Annual Meeting of the Atomic Energy Society of Japan, March 2003, Japan

Key Words: 2D/1D fusion method, CMFd, pCMFd, MOC, acceleration (pdf)59. Cho, N.Z. and Chang Je Park, "Comparison of Coarse Mesh Rebalance and Coarse Mesh Finite Difference Acceleration for the Neutron Transport Calculation", Nuclear Mathematical and Computational Sciences M&C(2003), April 2003, Gatlinburg, Tennessee, U.S.A (CD-ROM)

60. Park, Y.R. and Cho, N.Z., "Angular Dependent Coarse-Mesh Rebalance Method for Acceleration of the Discrete Ordinates Neutron Transport Calculations ",Nuclear Mathematical and Computational Sciences M&C(2003), April 2003, Gatlinburg, Tennessee, U.S.A. (CD-ROM)

61. Park, Y.R. and Cho, N.Z., "Coarse-Mesh Angular Dependent Rebalance Acceleration Method for Transport Calculations in X-Y Geometry", 18'th International Conference on Transport Theory (18 ICTT), July 2003, Rio de Janeiro, RJ, Brazil

62. Lee, G.S. and Cho, N.Z., "An Approach of Super-Element Sweeping for the Solution of Neutron Transport Equation in Heterogeneous Geometry", The Physics of Fuel Cycles and Advanced Nuclear Systems: Global Developments PHYSOR 2004, April 2004, Chicago, USA (CD-ROM)

63. Park, Y.R. and Cho, N.Z., "The Method of Characteristics Neutron Transport Calculations Accelerated by Coarse-Mesh Angular Dependent Rebalance", SIAM Conference on Computational Science & Engineering, February 12-15 2005, Orlando, Florida, USA

64. Cho, N.Z., Lee, J.J., Do Sam Kim, Chae Yong Yang, and Jong Chull Jo, "Improved Features of the AFEN Method in Hexagonal-Z 3-D Geometry for Neutron Diffusion Calculation", Atomic Energy Society of Japan Spring Meeting, March 29-31 2005, Tokai University, Tokyo, Japan.

66. Lee, G.S. and Cho, N.Z., "Three-Dimensional Whole-Core Transport Calculation of the OECD Benchmark Problem C5G7 MOX by The CRX Code", Nuclear Mathematical and Computational Sciences M&C(2005), September 12-15, 2005, Avignon, France.

67. Park, Y.R. and Cho, N.Z., "CMADR Acceleration and Its Convergence Analysis of the Method of Characteristics for Neutron Transport Calculation", Nuclear Mathematical and Computational Sciences M&C(2005), September 12-15, 2005, Avignon, France.

68. Kim, J.W., Cho, N.Z., Hyun-Kie Jang, Byung-Il Choi, and Heung-Young Lee, "A Preliminary Study of Burnup Credit Applied to Criticality Analysis of Spent Fuels", Proceedings of International Symposium on Radiation Safety Management, pp.506-517, November 2-4, 2005, Daejeon, Korea.

69. Lee, J.J., Lee, J.H., Han Jong Yoo, Lee, G.S. and Cho, N.Z., "TOPS Nodal Code Solutions for the OECD/PBMR-400 Benchmark Problem", Advances in Nuclear Analysis and Simulation PHYSOR 2006, September 10-14, 2006, Vancouver, Canada (CD-ROM)

70. Cho, N.Z. and Hui Yu, "Monte Carlo Simulation Models for Randomly Distributed Particle Fuels with Packing Fraction Variability Based on a Sub-Fine Lattice System", 2007 Annual Meeting of the Atomic Energy Society of Japan, March 27-29, 2007, Nagoya University, Japan.

71. Yoo, H.J., and Cho, N.Z., "Coarse Mesh Rebalance Acceleration Revisited: Krylov Preconditioning", Joint International Topical Meeting on Mathematics & Computation and Supercomputing in Nuclear Applications (M&C+SNA 2007), April 15-19, 2007, Monterey, U.S.A.

72. B.G. Hong, W. K. In, Y.Kim, D.W. Lee, K.W. Song, K.H. Yoon, S. Cho, M.Y. Ahn, D.H. Kim, S. Yun, and N.Z. Cho, "Progress in the Design of a Tritium Breeding Blankets for Testing in ITER," 21st IAEA Fusion Energy Conference, October 2006, Chengdu, China.

73. Seungyon Cho, Mu-Young Ahn, Eun-Seok Lee, Sunghwan Yun, Nam Zin Cho, and Ki Jung Jung, Current Status of Design and Analysis of Korea Helium Cooled Solid Breeder Test Blanket Module, Heidelberg, Germany, ISFNT-8, 2007.

74. Sunghwan Yun, Nam Zin Cho, Mu-Young Ahn, Seungyon Cho, Depletion Analysis of a Solid Type Blanket Design for ITER, Heidelberg, Germany, ISFNT-8, 2007.

75. Mu-Young Ahn, Seungyon Cho, Duck Hoi Kim, Eun-Seok Lee, Hyung-Seok Kim, Jae-Seung Suh, Sunghwan Yun, Nam Zin Cho, Preliminary Safety Analysis of Korea Helium Cooled Solid Breeder Test Blanket Module, Heidelberg, Germany, ISFNT-8, 2007.

76. Jong Woon Kim, Nam Zin Cho, Sang-Jin Lee and Hyun Kie Jang, "Criticality Analysis for the Conceptual Spent Fuel Dry Storage with Burnup Credit", Proceedings of International Symposium on Radiation Safety Management, pp.619-628, November 7-9, 2007, Daejeon, Korea.

77. Sunghwan Yun, Jong Woon Kim, and Nam Zin Cho, "Monte Carlo Space-Time Reactor Kinetics Method and Its Verification with Time-Dependent Sn Method", A Sustainable Resource PHYSOR 2008, submitted.

78. Jae Hoon Song and Nam Zin Cho, "Monte Carlo Calculation of Temperature Distributions in a Pebble with Dispersed Fuel Particles," ARWIF-2008, Fukui, Japan, February 20-22, 2008

**[Domestic Conference Papers]**

1. Cho, N.Z., "Chernobyl : Nonlinear Reactor Analysis Revisited," Special Lecture, Proceedings of the Korean Nuclear Society Annual Meeting, October 1987, Seoul.

2. Yang, C.Y., Cho, N.Z., "On the Multiplicity of Power Distributions in a Nuclear Reactor under Reactivity Feedback Effects," Proceedings of the Korean Nuclear Society Annual Meeting, October 1987, Seoul.

3. Jung, W.S., Cho, N.Z., "SLIM/SVD - A Computer Code for Evaluation of System-Level Importance Measures in Probabilistic Safety Analysis of Nuclear Power Plants," Proceedings of the Korean Nuclear Society Annual Meeting, May 1988, Seoul.

4. Jeong, H.Y., Cho, N.Z., "A Spectral Form Function Method for Reconstructing Pointwise Flux Distributions," Proceedings of the Korean Nuclear Society Annual Meeting, May 1988, Seoul.

5. Woo, H.S., Cho, N.Z., "Optimal Control of Xenon concentration via Observer Design," Proceedings of the Korean Nuclear Society Annual Meeting, May 1989, Suwon.

6. Na, W.J., Cho, N.Z., "Maximum Entropy Method for the Reconstruction Problem in Nodal Calculation : Preliminary Results," Proceedings of the Korean Nuclear Society Annual Meeting, May 1989, Suwon.

7. Jung, W.S., Cho, N.Z. "MARADD - A Computer Code for Semi-Markov Reliability Analysis of Test/Repair Policies for Standby Safety Systems," Proceedings of the Korean Nuclear Society Annual Meeting, May 1989, Suwon.

8. Lee, K.N., Cho, N.Z., "MARAS - A Computer Code for Semi-Markov Reliability Analysis of Alternating Systems, Proceedings of the Korean Nuclear Society Annual Meeting, May 1989, Suwon.

9. Jung, W.S., Cho, N.Z., "An Improved Maximum Entropy Method for the Reconstruction Problem in Nodal Calculation," Proceedings of the Korean Nuclear Society Annual Meeting, October 1989, Seoul.

10. Park, Y.H., Cho, N.Z., "An Observer-Theoretic Approach to Estimating Neutron Flux Distribution," Proceedings of the Korean Nuclear Society Annual Meeting, October 1989, Seoul.

11. Kim, Y.H., Cho, N.Z., "A Flux- and Adjoint Flux-Weighting Method for the Control Rod Cusping Problem in Nodal Methods," Proceedings of the Korean Nuclear Society Spring Annual Meeting, May 1990, Pohang.

12. Lee, Y.J., Cho, N.Z., "KIGEN - A Computer Code for Decay Heat Calculation by Analytic Relations," Proceedings of the Korean Nuclear Society Spring Annual Meeting, May 1990, Pohang.

13. Choi, J.S., Cho, N.Z., "Variance Reduction Techniques for Uncertainty Analysis of Fault Trees," Proceedings of the Korean Nuclear Society Spring Annual Meeting, May 1990, Pohang.

14. Kim, Y.H., Cho, N.Z., "Solution of Neutron Diffusion Equation on a Parallel Computer," Proceedings of the Korean Nuclear Society Spring Annual Meeting, pp.75-80, May 1991, Taejon.

15. Park, B.H., Cho, N.Z., "A Compute Code for Common-Cause Failure Analysis," Proceedings of the Korean Nuclear Society Spring Annual Meeting, pp.341-346, May 1991, Taejon.

16. Chang, D.I., Cho, N.Z., "An Analytic Relations Method for the Calculation of Actinides Concentrations," Proceedings of the Korean Nuclear Society Spring Annual Meeting, pp.499-504, May 1991, Taejon.

17. Kim, Y.H., Cho, N.Z. "Domain Decomposition Solution of the Neutron Diffusion Equation with an Iterative Parallel Algorithm on a Transputer Network," Proceedings of the Korean Nuclear Society Autumn Annual Meeting, pp.125-130, October 1991, Suwon.

18. Park, Y.H., Cho, N.Z., "Infinite-Dimensional Observer Theory for Dynamic Estimation of Neutron Flux and Xenon Distributions," Proceedings of the Korean Nuclear Society Autumn Annual Meeting, pp. 131-136, October 1991, Suwon.

19. Cho, N.Z., Kim, Y.H., and Song, J.S., "Supercomputing with Parallel Computers in Reactor Analysis," Proceedings of the 7th KAIF/KNS Annual Conference, pp.465-472, April 1992, Seoul.

20. Ahn, J.G., Cho, N.Z., "Generation of Spatial Weighting Functions for Ex-Core Detectors by Adjoint Transport Calculation," Proceedings of the Korean Nuclear Society Spring Meeting, pp.15-20, May 1992, Kori.

21. Cho, Y.C., Cho, N.Z., "Adomian Decomposition Method for the Reactor Point Kinetics," Proceedings of the Korean Nuclear Society Spring Meeting, pp.67-72, May 1992, Kori.

22. Yang, C.Y., Cho, N.Z., "An Expansion Method for Determining Asymptotic Stability Domains of Nonlinear Reactors," Proceedings of the Korean Nuclear Society Spring Meeting, pp.447-452, May 1992, Kori.

23. Kim, D.S., Cho, N.Z., "Generation of Gamma-Ray Streaming Kernels Through Cylindrical Ducts via Monte Carlo Method," Proceedings of the Korean Nuclear Society Spring Meeting, pp.667-672, May 1992, Kori.

24. Kim, Y.H., Cho, N.Z., "Convergence Analysis of the Parallel Schwarz Algorithm with Under-Relaxation in Pseudo- Boundary Conditions," Proceedings of the Korean Nuclear Society Autumn Meeting, pp.223-228, October 1992, Seoul.

25. Park, M.G., Cho. N.Z., "Nonlinear Model-Based Robust Control of a Nuclear Reactor Using Adaptive PIF Gains and Variable Structure Controller," Proceedings of the Korean Nuclear Society Autumn Meeting, pp.285-290, October 1992, Seoul.

26. Chang, S.H., Baek, W.P., Lee, S.W., No, H.C., and Cho, N.Z., "A Proposed Concept of Passive Pressurized Water Reactor Based on Existing Reactor Coolant System Design," Proceedings of the Korean Nuclear Society Autumn Meeting, pp.431-436, October 1992, Seoul.

27. Noh, J.M., Cho, N.Z., "A New Nodal Method : Approach of Analytic Basis Function Expansion," Proceedings of the Korean Nuclear Society Spring Meeting, pp.13-18, May 1993, Kwangju.

28. Park, M.G., Cho, N.Z., "Gaussian Function Neural Network-Based Self-Tuning Control of KMRR," Proceedings of the Korean Nuclear Society Spring Meeting, pp.297-302, May 1993, Kwangju.

29. Noh, J.M., Cho, N.Z., "Application of Analytic Function Expansion Nodal Method to Analysis of MOX Assembly Loaded Reactor Cores," Proceedings of the Korean Nuclear Society Autumn Meeting, pp.293-298, October 1993, Seoul.

30. Cho, N.Z., Jo, C.K., "Effects of Inter-Assembly Spectral Interaction in MOX Cores Analyzed by CASMO-3M/AFEN," Proceedings of the Korean Nuclear Society Spring Meeting, Vol.1, pp.23-28, May 1994, Pohang.

31. Kim, Y.H., Cho, N.Z., "Parallel Sn Transport Calculation on a Transputer Network," Proceedings of the Korean Nuclear Society Spring Meeting, Vol.1, pp.29-34, May 1994, Pohang.

32. Cho, N.Z., Hong, S.K., "The Method of Streaming Rays for Neutron Transport Problems," Proceedings of the Korean Nuclear Society Spring Meeting, Vol.1, pp.67-72, May 1994, Pohang.

33. Park, C.J., Cho, N.Z., "Wavelet Theory for Solution of the Neutron Diffusion Equation," Proceedings of the Korean Nuclear Society Autumn Meeting, Vol.1, pp.79-84, October 1994, Seoul.

34. Noh, J.M., Cho, N.Z., "Burnup Gradient Correction Model Implemented in the AFEN Code," Proceedings of the Korean Nuclear Society Autumn Meeting, Vol.1, pp.85-92, October 1994, Seoul.

35. Kim, T.H., Cho, N.Z., "SPANDOM - Source Projection Analytic Nodal Discrete Ordinates Method," Proceedings of the Korean Nuclear Society Autumn Meeting, Vol.1, pp.111-116, October 1994, Seoul.

36. Park, K.W., Cho, N.Z., "Waveform Relaxation Method for Reactor Transient Analysis," The 10th KAIF/KNS Annual Conference, April 1995, Seoul.

37. Cho, N.Z., "The Nodal Methods in Reactor Core Nuclear Design," Special Lecture, Proceedings of the Korean Nuclear Society Spring Meeting, Vol.1, pp.45-53, May 1995, Ulsan.

38. Cho, N.Z., Kim, D.S., "On the AFEN Method for Triangular Nodes in Hexagonal Assembly Cores," Proceedings of the Korean Nuclear Society Spring Meeting, Vol.1, pp.25-30, May 1995, Ulsan.

39. Hong, S.G., Cho, N.Z., and Noh, J.M., "Development of a Three-Dimensional Nodal Diffusion Code Based on the AFEN Methodology," Proceedings of the Korean Nuclear Society Spring Meeting, Vol.1, pp.77-82, May 1995, Ulsan.

40. Cho, N.Z., Noh, J.M., "A Multigroup Diffusion Nodal Scheme : Hybrid of AFEN and PEN Methods," Proceedings of the Korean Nuclear Society Autumn Meeting, Vol.1, pp.29-34, October 1995, Seoul.

41. Cho, N.Z., Hong, S.G., "CRX : A Characteristic Transport Theory Code for Cell and Assembly Calculations in Reactor Core Design," Proceedings of the Korean Nuclear Society Autumn Meeting, Vol.1, pp.85-90, October 1995, Seoul.

42. Kim, Y.B., Cho, N.Z., "Design Charateristics of Moderation- Enhanced Reactor Core Loaded 100% with MOX Fuel," The 11th KAIF/KNS Annual Conference, March 1996, Seoul.

43. Cho, N.Z., Kim, Y.H., "Code System Development for Analysis of the Fast Transmutation Reactors," Proceedings of the Korean Nuclear Society Autumn Meeting, Vol.1, pp.91-96, October 1995, Seoul.

44. Cho, N.Z., Hong, S.G., "CRX-Hex : A Transport Theory Code Based on Characteristic Method for Hexagonal Geometry," Proceedings of the Korean Nuclear Society Spring Meeting, Vol.1, pp.28-33, May 1996, Cheju.

45. Cho, N.Z., Kim, Y.H., and Park, K.W., "Extension of AFEN Methodology to Multigroup Problems in Hexagonal-Z Geometry," Proceedings of the Korean Nuclear Society Spring Meeting, Vol.1, pp.137-141, May 1996, Cheju.

46. Cho, N.Z., Kim, D.S, and Kim, Y.H., "A New Approach to Treating Baffle/Reflector Heterogenity in AFEN Methology," Proceedings of the Korean Nuclear Society Spring Meeting, Vol.1, pp.148-153, May 1996, Cheju.

47. Cheng, H.W., Cho, N.Z., "A Spectral-Galerkin Nodal Method for Solving the Two-Dimensional Multigroup Diffusion Equations," Proceedings of the Korean Nuclear Society Spring Meeting, Vol.1, pp.157-162, May 1996, Cheju.

48. Park, C. J., Cho, N.Z., "Fast Solution of Linear Systems by Wavelet Transform," Proceedings of the Korean Nuclear Society Spring Meeting, Vol.1, pp.282-287, May 1996, Cheju.

49. Lee, S.H., Cho, N.Z., "Delayed Hopfield-like Neural Network for Solving Inverse Radiation Transport Problems," Proceedings of the Korean Nuclear Society Autumn Meeting, Vol.1, pp.21-26, November 1996, Taejon.

50. Cho, N.Z, Cheng, H.W., and Park, C.J., "Boundary Element Method for the Homogenization of the Baffle/Reflector," Proceedings of the Korean Nuclear Society Autumn Meeting, Vol.1, pp.27-32, November 1996, Taejon.

51. Hong, S.G., Cho, N.Z., "FN-Based Nodal Transport Method in X-Y Geometry," Proceedings of the Korean Nuclear Society Autumn Meeting, Vol.1, pp.39-44, November 1996, Taejon.

52. Park, C.J, Cho, N.Z., "Reactivity Condition Monitoring Via Wavelet Transform De-noising," Proceedings of the Korean Nuclear Society Autumn Meeting, Vol.1, pp.67-72, November 1996, Taejon.

53. Cho, N.Z., Lee, K.T., "Design Analysis of a Thorium Fueled Reactor with Seed-Blanket Assembly Configuration," Proceedings of the Korean Nuclear Society Spring Meeting, Vol.1, pp.21-26, May 1997, Kwangju.

54. Cho, N.Z., Lee, K.H., and Kim, Y.H., "An Efficient Multigrid Algorithm for the Reactor Eigenvalue Problems," Proceedings of the Korean Nuclear Society Spring Meeting, Vol.1, pp.27-32, May 1997, Kwangju.

55. Cho, N.Z., Kim, D.S, "Stability Analysis of an Accelerator Driven Fluid-Fueled Subcritical Reactor System," Proceedings of the Korean Nuclear Society Spring Meeting, Vol.1, pp.90-95, May 1997, Kwangju.

56. Park, J.H., Cho, N.Z., "Design of a Medical Reactor Generating High Quality Neutron Beams for BNCT," Proceedings of the Korean Nuclear Society Spring Meeting, Vol.2, pp.427-432, May 1997, Kwangju.

57. Park, Y.R., Cho, N.Z., "Nuclear Data Compression and Reconstruction via Discrete Wavelet Transform," Proceedings of the Korean Nuclear Society Autumn Meeting, Vol.1, pp.225-230, October 1997, Taegu.

58. Koh, D.J., Jo, C.K., Cho, N.Z., etc., "The Use of Burnup Credit in Criticality Control for the Korean Spent Fuel Management Program," Proceedings of the Korean Nuclear Society Autumn Meeting, Vol.2, pp.245-250, October 1997, Taegu.

59. Cho, N.Z, Hong, S.G., Kim, T.H., et al., "Fuel Self-Sufficient and Low Proliferation Risk Multi-Recycling of Spent Fuel," The 13th KAIF/KNS Annual Conference, p.417, April 1998, Seoul.

60. Lee, K.T., Cho, N.Z., "Evaluation of U-Zr Hydride Fuel for a Thorium Fuel Cycle in an RTR Concept," Proceedings of the Korean Nuclear Society Spring Meeting, Vol.1, pp.52-57, May 1998, Suwon.

61. Moon, K.S., Cho, N.Z., Noh, J.M., and Hong, S.G.., "Acceleration of the AFEN Method by Two-Node Nonlinear Iteration," Proceedings of the Korean Nuclear Society Spring Meeting, Vol.1, pp.87-92, May 1998, Suwon.

62. Koh, D.J., Jo, C.K., Ryu, H.G., Cho, N.Z., et al., "Analysis of the Nuclear Subcriticality for the High Density Spent Fuel Storage at PWR Plants," Proceedings of the Korean Nuclear Society Spring Meeting, Vol.2, pp.470-475, May 1998, Suwon.

63. Park, C.J., Park, J.H., and Cho, N.Z., "Multigrid Wavelet-Based Natural Pixel Method for Image Reconstruction in Emission Computed Tomography," Proceedings of the Korean Nuclear Society Spring Meeting, Vol.2, pp.705-710, May 1998, Suwon.

64. Hong, S.G., Cho, N.Z., "Angular Dependent Rebalance Factor Method for Solving the SN Transport Equations in X-Y Geometry," Proceedings of the Korean Nuclear Society Autumn Meeting, Vol.1, p.47, Autumn 1998, Seoul.(Full Paper in CD-ROM)

65. Kim, D.S., Cho, N.Z., "Two-Node Nonlinear Iterative AFEN Method in Three-Dimensional Geometry," Proceedings of the Korean Nuclear Society Autumn Meeting, Vol.1, p.49, Autumn 1998, Seoul.(Full Paper in CD-ROM)

66. Seo, C.G., Park, C.J., Cho, N.Z., and Kim, H.R., "Pin Power Reconstruction from the HANARO Fuel Assembly Gamma Scanning," Proceedings of the Korean Nuclear Society Autumn Meeting, Vol.1, p.56, Autumn 1998, Seoul.(Full Paper in CD-ROM)

67. Koh, D.J., Cho, N.Z., etc, "Burnup Effects of MOX Fuel Pincells in PWR," Proceedings of the Korean Nuclear Society Autumn Meeting, Vol.1, p.64, Autumn 1998, Seoul.(Full Paper in CD-ROM)

68. Park, J.H., Cho, N.Z., and Kim, M.S., "A Benchmark of Beowulf Cluster for Nuclear Engineering Advanced Computation," Proceedings of the Korean Nuclear Society Spring Meeting, Vol.1, p.7, Spring 1999, Pohang.(Full Paper in CD-ROM)

69. Woo, S.W., Cho, N.Z., and Noh, J.M., "A Refinement of the Analytic Function Expansion Nodal Method with Interface Flux Moments," Proceedings of the Korean Nuclear Society Spring Meeting, Vol.1, p.17, Spring 1999, Pohang.(Full Paper in CD-ROM)

70. Kim, H.H. and Cho, N.Z., "Criticality Calculation for Cluster Fuel Bundles Using Monte Carlo Generated Grey Dancoff Factor," Proceedings of the Korean Nuclear Society Spring Meeting, Vol.1, p.17, Spring 1999, Pohang.(Full Paper in CD-ROM)

71. Chi, S.G. and Cho, N.Z., "Application of H-infinity Control Theory to PWR Power Control," Proceedings of the Korean Nuclear Society Spring Meeting, Vol.1, p.17, Spring 1999, Pohang.(Full Paper in CD-ROM)

72. Kim, G.G. and Cho, N.Z., "A Study on the Signal Processing of the Senstivity Depletion Laws for Rhodium Self-Powered Neutron Detectors (SPNDs)," Proceedings of the Korean Nuclear Society Spring Meeting, Vol.1, p.17, Spring 1999, Pohang.(Full Paper in CD-ROM)

73. Hong, S.G. and Cho, N.Z., "Generation of the Analytic Solutions of the Multigroup Discrete Ordinates Transport Equation in Slab Geometry by Using Infinite Medium Green's Function," Proceedings of the Korean Nuclear Society Autumn Meeting, Vol.1, p.47, October 1999, Seoul.(Full Paper in CD-ROM)

74. Lee, G.S., Cho, N.Z., and Hong, S.G., "Acceleration of the Method of Characteristics in the CRX Lattice Calculation Code for Anisotropic Scattering Problems," Proceedings of the Korean Nuclear Society Autumn Meeting, Vol.1, p.49, October 1999, Seoul.(Full Paper in CD-ROM)

75. Lee, G.S., Cho, N.Z., and Hong, S.G., "Whole-Core Heterogeneous Transport Calculations and Their Comparison with Diffusion Results," Proceedings of the Korean Nuclear Society Spring Meeting, May 2000, Kori.(Full Paper in CD-ROM)

76. Kim, D.S. and Cho, N.Z., "Space-Dependent Feedback Kinetics Calculation in the Anayltic Function Expansion Nodal Method," Proceedings of the Korean Nuclear Society Spring Meeting, May 2000, Kori.(Full Paper in CD-ROM)

77. Park, C.J. and Cho, N.Z., "A Linear Multiple Balance Method for Discrete Ordinates Neutron Transport Equations," Proceedings of the Korean Nuclear Society Autumn Meeting, October 2000, Taejon.(Full Paper in CD-ROM)

78. Park, K.W. and Cho, N.Z., "The p-version of the Finite Element Method and Domain Decomposition Approach for Two-Dimensional Diffusion Equations," Proceedings of the Korean Nuclear Society Autumn Meeting, October 2000, Taejon.(Full Paper in CD-ROM)

79. Noh, J.M., Joo, H.K., Yoo, J.W., and Cho, N.Z., "Inter-Assembly Thermal Flux Gradient Correction of Homogenization Parameters Based on One-Dimensional Heterogeneous Interface Model," Proceedings of the Korean Nuclear Society Spring Meeting, May 2001, Cheju.(Full Paper in CD-ROM)

80. Choi, Y.K. and Cho, N.Z., "Improved Negative Fixup with Cell Rebalance for Boltzmann-Fokker-Planck Transport Equation," Proceedings of the Korean Nuclear Society Spring Meeting, May 2001, Cheju.(Full Paper in CD-ROM)

81. Jeong, C.J., Choi, H.B., and Cho, N.Z., "An Optimal Fuel Management Method Based on CANDU In-Core Detector Readings," Proceedings of the Korean Nuclear Society Spring Meeting, May 2001, Cheju.(Full Paper in CD-ROM)

82. Kim, S.J., Kim Y.I., Kim, Y.J., and Cho, N.Z., "A Transition Cycle Strategy to Enhance Minor Actinide Burning Potential in the Pan-Shape LMR Core," Proceedings of the Korean Nuclear Society Spring Meeting, May 2001, Cheju.(Full Paper in CD-ROM)

83. Park, C.J. and Cho, N.Z., "The Additive Angular Rebalance Acceleration Method for Solving Neutron Transport Equations in X-Y Geometry," Proceedings of the Korean Nuclear Society Spring Meeting, May 2001, Cheju.(Full Paper in CD-ROM)

84. Kim, J.W. and Cho, N.Z., "Generation of Isotropic and Anisotropic Scattering Cross Sections for Boltzmann-Fokker- Planck Equation via Decomposition and Minimized RMS Errors," Proceedings of the Korean Nuclear Society Autumn Meeting, October 2001, Suwon.(Full Paper in CD-ROM)

85. Jung, D.H. and Cho, N.Z., "A Spectral Analytic Discrete- Ordinates Transport Method Based on Infinite Medium Green's Function for Multiplying Fission Source Problems," Proceedings of the Korean Nuclear Society Autumn Meeting, October 2001, Suwon.(Full Paper in CD-ROM)

86. Park, C.J. and Cho, N.Z., "A New Acceleration Method of Additive Dependnet Rebalance with Extrapolation for Discrete Ordinates Transport Equation," Proceedings of the Korean Nuclear Society Autumn Meeting, October 2001, Suwon.(Full Paper in CD-ROM)

87. Cho, N.Z., Lee, G.S., and Park, C.J., "A Fusion Technique of 2-D/1-D Methods for Three-Dimensional Whole-Core Transport Calculations," Proceedings of the Korean Nuclear Society Spring Meeting, May 2002, Kwangju.(Full Paper in CD-ROM

88. Kim, D.S. and Cho, N.Z., "Analytic Function Expansion Nodal Method in R-Z Coordinates for Analysis of PBMR Cores," Proceedings of the Korean Nuclear Society Spring Meeting, May 2002, Kwangju.(Full Paper in CD-ROM)

89. Park, Y.R., and Cho, N.Z., "Angular Dependent Coarse-Mesh Rebalance Method for Acceleration of the Discrete Ordinates Neutron Transport Equation," Proceedings of the Korean Nuclear Society Autumn Meeting, October 2002, Yongpyong.(Full Paper in CD-ROM)

90.Cho, N.Z. and Lee, G.S., "Comparison of CMFD and p-CMFD Acceleration Method for Neutron Transport Calculations," Proceedings of the Korean Nuclear Society Spring Meeting, June 2003, Gyeongju.(Full Paper in CD-ROM)

91.Park, Y.R. and Cho, N.Z., "Coarse-Mesh Angular Dependent Rebalance Acceleration Method in X-Y Geometry," Proceedings of the Korean Nuclear Society Spring Meeting, June 2003, Gyeongju.(Full Paper in CD-ROM)

92. Lee, G.S. and Cho, N.Z., "A Superelement-Sweeping Method for Neutron Transport Calculations in Heterogeneous Geometry," Proceedings of the Korean Nuclear Society Autumn Meeting, October 2003, Yongpyong.(Full Paper in CD-ROM)

93. Yun, S.H. and Cho, N.Z., "Semi-Analog Monte Carlo (SMC) Method for Time-Dependent Three-Dimensional Heterogeneous Radiative Transfer Problems," Proceedings of the Korean Nuclear Society Autumn Meeting, October 2003, Yongpyong.(Full Paper in CD-ROM)

94. Cho, N.Z., Yun, S.H., Lee, K.T., and Lee, G.S., "An Adjoint p-CMFD Scheme for Monte Carlo k-Eigenvalue Calculations," Proceedings of the Korean Nuclear Society Spring Meeting, May 2004, Gyeongju.(Full Paper in CD-ROM)

95. Lee, K.T. and Cho, N.Z., "A Spectrum Correction Method for Fuel Assembly Rehomogenization," Proceedings of the Korean Nuclear Society Spring Meeting, May 2004, Gyeongju.(Full Paper in CD-ROM)

96. Park, Y.R. and Cho, N.Z., "The MOC Neutron Transport Calculations Accelerated by Coarse-mesh Angular Dependent Rebalance," Proceedings of the Korean Nuclear Society Autumn Meeting, p.81-82, October 2004, Yongpyong.

97. Lee, G.S., Lee, K.T., Cho, N.Z., Kim, Y.H., and Jeon, K.L., "An Optimization Study of Gadolinia Burnable Absorber Design for Westinghouse Type 16×16 Fuel Assembly," Proceedings of the Korean Nuclear Society Autumn Meeting, p.123-124, October 2004, Yongpyong.

98. Kim, J.W. and Cho, N.Z., "Generating Nonnegative Multigroup Scattering Cross Sections with Monte Carlo Simulation", Proceedings of the Korean Nuclear Society Spring Meeting, CD-ROM, May 26-27, 2005, Jeju.

99. Cho, N.Z., Lee, J.H., Lee, J.J., and Do Sam Kim, "Development of an AFEN Method Code in cylindrical (r,theta,z) Geometry for Design Analysis of Pebble Bed Modular Reactor", Proceedings of the Korean Nuclear Society Spring Meeting, CD-ROM, May 26-27, 2005, Jeju.

100. Yong Ryong Park and Cho, N.Z., "Convergence Analysis of CMADR Acceleration for the Method of Characteristics", Proceedings of the Korean Nuclear Society Spring Meeting, CD-ROM, May 26-27, 2005, Jeju.

101. Cho, N.Z. and Hui Yu, "Analysis of VHTR Fuel Compact Cell Using Fine-Lattice Stochastic Modeling", Proceedings of the Korean Nuclear Society Spring Meeting, CD-ROM, May 26-27, 2005, Jeju.

102. Yun, S.H. and Cho, N.Z., "Comparison of LCLS Algorithm and MCNP/CFP Code for Analysis of VHTR Fuel Elements with Randomly Distributed Particles", Proceedings of the Korean Nuclear Society Spring Meeting, CD-ROM, May 26-27, 2005, Jeju.

103. Qian Hong and Cho, N.Z., "Molecular Dynamics Simulation of Thermomechanical Properties of Mononitride Nuclear Fuel", Proceedings of the Korean Nuclear Society Spring Meeting, CD-ROM, May 26-27, 2005, Jeju.

104. Cho, N.Z., Lee, J.H., Lee, J.J., and Do Sam Kim, "Verification of the Analytic Function Expansion Nodal (AFEN) Method in Cylindrical (r,theta,z) Geometry for Pebble Bed Reactors", Proceedings of the Korean Nuclear Society Autumn Meeting, CD-ROM, October 27-28, 2005, Busan.

105. Jong Soo Choi and Cho, N.Z., "Evaluation of Truncation Error in Minimal Cut Set-Based Fault Tree Analysis", Proceedings of the Korean Nuclear Society Autumn Meeting, CD-ROM, October 27-28, 2005, Busan.

106. Lee, J.J., Lee, G.S. and Cho, N.Z., "The AFEN Method in Cylindrical (r,theta,z) Geometry for Pebble Bed Reactors - Extension to Treatment of Void Regions -", Proceedings of the Korean Nuclear Society Spring Meeting, CD-ROM, May 25-26, 2006, Chuncheon.

107. Cho, N.Z. and Liangzhi Cao, "Wavelet-theoretic Method for Solution of Neutron Transport Equation", Proceedings of the Korean Nuclear Society Spring Meeting, CD-ROM, May 25-26, 2006, Chuncheon.

108. Cho, N.Z. and Yu Hui, "Sub-fine Lattice Stochastic Modeling of Randomly Distributed Particle Fuels with Variability in Packing Fraction", Proceedings of the Korean Nuclear Society Autumn Meeting, CD-ROM, November 2-3, 2006, Gyeongju, Korea.

109. Kim, J.W., Cho, N.Z., Lee, S.J., and Baeg, C.Y., "Estimation of the Fuel Depletion Code Bias and Uncertainty in Burnup-credit Criticality Analysis", Proceedings of the Korean Nuclear Society Autumn Meeting, CD-ROM, November 2-3, 2006, Gyeongju, Korea.

110. Hong, S.G., Cho, N.Z., Kim, K.S., and Song, J.S., "A Rapidly Convergent Generalized Rebalance Method (GRM) for Discrete Ordinates Transport Equations", Proceedings of the Korean Nuclear Society Spring Meeting, CD-ROM, May 10-11, 2007, Jeju, Korea.

111. J.H. Song, and Cho, N.Z., "An Improved Monte Carlo Method for Solving Heat Conduction Problems with Complex Geometry", Proceedings of the Korean Nuclear Society Spring Meeting, CD-ROM, May 10-11, 2007, Jeju, Korea.

112. Cho, N.Z., and Hui Yu, "A New Approach to Effective Thermal Conductivity for VHTR Fuels", Proceedings of the Korean Nuclear Society Spring Meeting, CD-ROM, May 10-11, 2007, Jeju, Korea.

113. Jaejun Lee and Nam Zin Cho, "The AFEN Method in Cylindrical (r,theta,z) Geometry for Pebble Bed Reactors - Incorporation of Acceleration and Discontinuity Factor -", Proceedings of the Korean Nuclear Society Autumn Meeting, CD-ROM, October 25-26, 2007, PyeongChang, Korea.

114. Han Jong Yoo and Nam Zin Cho, "Preconditioners for Krylov Iterative Method for Two-Dimensional MOC Problems", Proceedings of the Korean Nuclear Society Autumn Meeting, CD-ROM, October 25-26, 2007, PyeongChang, Korea.

115. Jae Hoon Song and Nam Zin Cho, "An Improved Monte Carlo Method Applied to Heat Conduction Problem of a Fuel Pebble", Proceedings of the Korean Nuclear Society Autumn Meeting, CD-ROM, October 25-26, 2007, PyeongChang, Korea.

116. M. Y. Ahn, S. Cho, D. H. Kim, E. S. Lee, H. S. Kim, J. S. Suh, S. Yun, N. Z. Cho, "Preliminary Analysis on Decay Heat Removal Capability of Helium Cooled Solid Breeder Test Blanket Module", Proceedings of the Korean Nuclear Society Autumn Meeting,, October 25-26, 2007, PyeongChang, Korea.

117. Nam Zin Cho, Hui Yu and Jong Woon Kim, "Thermal Transient Analysis of Pebble Fuels Based on the Two-Temperature Homogenized Model," Proceedings of the Korean Nuclear Society Spring Meeting, May 29-30, 2008, Gyeongju, Korea.

118. Odmaa Sambuu and Nam Zin Cho, "Burnup Analysis of Fuel Assembly Designs for the 300 kW Small Medical Reactor," Proceedings of the Korean Nuclear Society Spring Meeting, May 29-30, 2008, Gyeongju, Korea.

119. Nam Zin Cho and Hui Yu , "Shell-Fuel Pebble Design and Its Nuclear and Thermal Performance," Proceedings of the Korean Nuclear Society Autumn Meeting, CD-ROM, October 30-31, 2008, PyeongChang, Korea.

120. Sunghwan Yun and Nam Zin Cho, "A Monte Carlo Depletion Method with Leakage Corrected Critical Spectrum," Proceedings of the Korean Nuclear Society Spring Meeting, CD-ROM, May 22, 2009, Jeju, Korea.

121. Dongil Lee and Nam Zin Cho, "Incorporation of Truncation Errors in Auxiliary Feed Water System PSA by CUTREE," Proceedings of the Korean Nuclear Society Spring Meeting, CD-ROM, May 22, 2009, Jeju, Korea.

122. Nam Zin Cho, Sunghwan Yun, and Jaejun Lee, "2-D Extension of the Global-Local Iteration Method with Homogenization by Monte Carlo Based on Non-Zero Leakage Spectra," Proceedings of the Korean Nuclear Society Spring Meeting, CD-ROM, Oct 29-30, 2009, Gyeongju, Korea.

123. Woo Song Kim, Il Tak Woo, Sang Rin Shon, and Nam Zin Cho, "An Automated Calculation Program for the Axial Xenon Stability Index," Proceedings of the Korean Nuclear Society Spring Meeting, CD-ROM, Oct 29-30, 2009, Gyeongju, Korea.

124. Bumhee Cho and Nam Zin Cho, "Extension of Analytic Function Expansion Nodal (AFEN) Method for Multigroup Simplified P3 (SP3) Equations", Proceedings of the Korean Nuclear Society Spring Meeting, CD-ROM, May 27-28, 2010, Pyeongchang, Korea.

125. Yos P. Sitompul and Nam Zin Cho, "Parallelization with Ordered Sweep and Domain Decomposition in 2D and 3D SN Method", Proceedings of the Korean Nuclear Society Spring Meeting, CD-ROM, May 27-28, 2010, Pyeongchang, Korea.

126. Yoon Hee Lee and Nam Zin Cho, "Efficient and Accurate Calculation of Burnup Problems with Short-Lived Nuclides by a Krylov Subspace Method with the Newton Divided Difference," Proceedings of the Korean Nuclear Society Spring Meeting, CD-ROM, May 27-28, 2010, Pyeongchang, Korea.

127. Yoon Hee Lee and Nam Zin Cho, "A Krylov Subspace Method with Newton Divided Difference Applied to Depletion Calculation in ORIGEN 2.2," Proceedings of the Korean Nuclear Society Autumn Meeting, CD-ROM, October 21-22, 2010, Jeju, Korea

128. Han Jong Yoo and Nam Zin Cho, "A Krylov Subspace Method for Unstructured Mesh SN Transport Computation," Proceedings of the Korean Nuclear Society Autumn Meeting, CD-ROM, October 21-22, 2010, Jeju, Korea.

129. Jong Hyuck Won and Nam Zin Cho, "Discrete Ordinates Method-like Computation with Group Condensation and Angle Collapsing in Transport Theory," Proceedings of the Korean Nuclear Society Autumn Meeting, CD-ROM, October 21-22, 2010, Jeju, Korea.

130. Jaejun Lee, Jong Hyuck Won, Nam Zin Cho, Yong Ho Ryu, and Ju Yeop Park, "A Preliminary Analysis of SMART Reactor Core Using COREDAX Code," Proceedings of the Korean Nuclear Society Autumn Meeting, CD-ROM, October 21-22, 2010, Jeju, Korea.

131. Jong Hyuck Won and Nam Zin Cho, "Few-Group Transport Analysis of the Core-Reflector Problem in Fast Reactor Cores via Equivalent Group Condensation and Local/Global Iteration," Proceedings of the Korean Nuclear Society Spring Meeting, CD-ROM, May 26-27, 2011, Taebaek, Korea.

132. Sunghwan Yun and Nam Zin Cho, "A Cross Section Adjustment Method for Double Heterogeneity Problem in VHTGR Analysis," Proceedings of the Korean Nuclear Society Spring Meeting, CD-ROM, May 26-27, 2011, Taebaek, Korea.

133. Jaejun Lee, Jong Hyuck Won, Nam Zin Cho, Yong Ho Ryu, and Ju Yeop Park, "Preliminary Steady State and Transient Analyses of SMART Reactor Core Using COREDAX Code," Proceedings of the Korean Nuclear Society Spring Meeting, CD-ROM, May 26-27, 2011, Taebaek, Korea.

134. Yu Gwon Jo, and Nam Zin Cho, "Comparison of Monte Carlo Critical Spectra from B1 buckling Search and Albedo Search Methods - Preliminary Results," Proceedings of the Korean Nuclear Society Autumn Meeting, CD-ROM, October 27-28, 2011, Gyeongju, Korea.

135. Yoonhee Lee and Nam Zin Cho, "A Two-Block Decomposition Method for Efficient and Accurate Depletion Calculations," Proceedings of the Korean Nuclear Society Spring Meeting, CD-ROM, May 16-18, 2012, Jeju, Korea.

136. Nam Zin Cho, "The Partial Current-Based CMFD (p-CMFD) Method Revisited," Proceedings of the Korean Nuclear Society Autumn Meeting, CD-ROM, October 25-26, 2012, Gyeongju, Korea.

137. Seungsu Yuk and Nam Zin Cho, "Overlapping Local/Global Iteration for Whole-Core Transport Problems," Proceedings of the Korean Nuclear Society Autumn Meeting, CD-ROM, October 25-26, 2012, Gyeongju, Korea.