Iterative Two- and One-Dimensional Methods for Three-Dimensional Neutron Diffusion Calculations

REFERENCES

• H. FINNEMANN, F. BENNEWITZ, and M. R. WAGNER, “Interface Current Techniques for Multidimensional Reactor Calculation,” Atomkernenergie, 30, 123 (1977).
   Google Scholar
• K. S. SMITH, “An Analytic Nodal Method for Solving the Two-Group, Multi-Dimensional, Static and Transient Neutron Diffusion Equations,” Nuclear Engineering Thesis, Massachusetts Institute of Technology (1979).
   Google Scholar
• J. M. NOH and N. Z. CHO, “A New Approach of Analytic Basis Function Expansion to Neutron Diffusion Nodal Calculation,” Nucl. Sci. Eng., 116, 165 (1994).
   Web of Science ®Google Scholar
• H. C. LEE and C. H. KIM, “Unified Formulation of Nodal Expansion Method and Analytic Nodal Method Solutions to Two-Group Diffusion Equations,” Nucl. Sci. Eng., 138, 192 (2001).
   Web of Science ®Google Scholar
• H. C. LEE and C. H. KIM, “Unified Nodal Method Formulation for Analytic Function Expansion Nodal Method Solution to Two-Group Diffusion Equations in Rectangular Geometry,” Nucl. Sci. Eng., 140, 137 (2002).
   Web of Science ®Google Scholar
• K. KOEBKE, “A New Approach to Homogenization and Group Condensation,” IAEA Technical Committee Meeting on Homogenization Methods in Reactors Physics, IAEA-TECDOC-231, International Atomic Energy Agency (1978).
   Google Scholar
• K. S. SMITH, “Spatial Homogenization Methods for Light Water Reactor Analysis,” PhD Thesis, Massachusetts Institute of Technology (1980).
   Google Scholar
• K. KOEBKE and M. R. WAGNER, “The Determination of the Pin Power Distribution in a Reactor Core on the Basis of Nodal Coarse Mesh Calculations,” Atomkernergie, 30, 136 (1977).
   Google Scholar
• J. Y. CHO, H. G. JOO, K. KIM, and S. Q. ZEE, “Three-Dimensional Whole Core Transport Calculation Methodology of the DeCART Code,” KAERI/TR-2365/2003, KoreaAtomic Energy Research Institute (2003).
   Google Scholar
• 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).
   Web of Science ®Google Scholar
• H. G. JOO and J. Y. CHO, Korea Atomic Energy Research Institute, Private Communication (2003).
   Google Scholar
• 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).
   Web of Science ®Google Scholar
• G. R. CEFUS and E. W. LARSEN, “Stability Analysis of Coarse-Mesh Rebalance,” Nucl. Sci. Eng., 105, 31 (1990).
   Web of Science ®Google Scholar
• 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).
   Web of Science ®Google Scholar
• 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. M&C 2003, Gatlinburg, Tennessee, April 6-11, 2003, American Nuclear Society (2003) (CD-ROM).
   Google Scholar
• D. LEE, T. J. DOWNAR, and Y. KIM, “ConvergenceAnaly-sis of the Nonlinear Coarse Mesh Finite Difference Method,” Proc. M&C 2003, Gatlinburg, Tennessee, April 6-11, 2003, American Nuclear Society (2003) (CD-ROM).
   Google Scholar
• D. LEE, T. J. DOWNAR, and Y. KIM, “ConvergenceAnaly-sis of the Nonlinear Coarse-Mesh Finite Difference Method for One-Dimensional Fixed-Source Neutron Diffusion Problem,” Nucl. Sci. Eng., 147, 127 (2004).
   Web of Science ®Google Scholar
• 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. PHYSOR 2004, Chicago, Illinois, April 25-29, 2004, American Nuclear Society (2004) (CD-ROM).
   Google Scholar
• K. S. SMITH, “Nodal Method Storage Reduction by Nonlinear Iteration,” Trans. Am. Nucl. Soc., 44, 265 (1983).
   Google Scholar