REFERENCES
- S. K. GODUNOV and V. S. RYABENKII, Difference Schemes, North Holland Publishing Company, Amsterdam (1987).
- S. NAKAMURA, Applied Numerical Methods with Software, Prentice-Hall International, Inc. (1991).
- E. W. LARSEN, “Unconditionally Stable Diffusion-Synthetic Acceleration Methods for the Slab Geometry Discrete Ordinates Equations. Part I: Theory,” Nucl. Sci. Eng., 82, 47 (1982).
- T. NOH, W. F. MILLER, Jr., and J. E. MOREL, “The Even-Parity and Simplified Even-Parity Transport Equations in Two-Dimensional x-y Geometry,” Nucl. Sci. Eng., 123, 38 (1996).
- G. R. CEFUS and E. W. LARSEN, “Stability Analysis of Coarse-Mesh Rebalance,” Nucl. Sci. Eng., 105, 31 (1990).
- N. Z. CHO and C. J. PARK, “A Comparison of Coarse Mesh Rebalance and Coarse Mesh Finite Difference Accelerations for the Neutron Transport Calculations,” Proc. Int. Topl. Mtg. Nuclear Mathematical and Computational Sciences (M&C 2003), Gatlinburg, Tennessee, April 6–10, 2003, American Nuclear Society (2003) (CD-ROM).
- D. LEE, T. J. DOWNAR, and Y. KIM, “Convergence Analysis of the Nonlinear Coarse-Mesh Finite Difference Method,” Proc. Int. Topl. Mtg. Nuclear Mathematical and Computational Sciences (M&C 2003), Gatlinburg, Tennessee, April 6–10, 2003, American Nuclear Society (2003) (CD-ROM).
- D. LEE, T. J. DOWNAR, and Y. KIM, “Convergence Analysis of the Nonlinear Coarse-Mesh Finite Difference Method for One-Dimensional Fixed Source Neutron Diffusion Problem,” Nucl. Sci. Eng., 147, 127 (2004)
- H. C. LEE, D. LEE, and T. J. DOWNAR, “Convergence Analysis of 2-D/1-D Coupling Methods for the Three-Dimensional Neutron Diffusion Equation,” Proc. Int. Topl. Mtg. Physics of Fuel Cycles and Advanced Nuclear Systems: Global Developments (PHYSOR-2004), Chicago, Illinois, April 25–29, 2004, American Nuclear Society (2004) (CD-ROM).
- H. C. LEE, D. LEE, and T. J. DOWNAR, “Iterative 2-D/1-D Methods for 3-D Neutron Diffusion Calculations,” Nucl. Sci. Eng., 151, 46 (2005).
- H. C. LEE, J. M. NOH, H. K. JOO, D. LEE, and T. J. DOWNAR, “Fourier Convergence Analysis Applied to a Neutron Diffusion Eigenvalue Problem,” Proc. Int. Topl. Mtg. Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications (M&C 2005), Avignon, France, September 12–15, 2005, American Nuclear Society (2005).
- J. Y. CHO, H. G. JOO, K. KIM, and S. Q. ZEE, “Three-Dimensional Whole Core Transport Calculation Methodology of the DeCART Code,” KAERI0TR-236502003, Korea Atomic Energy Research Institute (2003).
- D. LEE, T. J. DOWNAR, and Y. KIM, “A Nodal and Finite Difference Hybrid Method for Pin-by-Pin Heterogeneous Three-Dimensional Light Water Reactor Diffusion Calculations,” Nucl. Sci. Eng., 146, 319 (2004).
- K. S. SMITH, “Nodal Method Storage Reduction by Nonlinear Iteration,” Trans. Am. Nucl. Soc., 44, 265 (1983).