REFERENCES
- R. SANCHEZ, J. MONDOT, Z. STANKOVSKI, A. COSSIC, and I. ZMIJAREVIC, “APOLLO II: A User-Oriented, Portable, Modular Code for Multigroup Transport Assembly Calculations,” Nucl. Sci. Eng., 100, 352 (1988).
- E. LEWIS and W. MILLER, Computational Methods of Neutron Transport, John Wiley and Sons, New York (1984).
- R. SANCHEZ and A. CHETAINE, “A Synthetical Acceleration for Two-Dimensional Characteristics Method in Unstructured Meshes,” Nucl. Sci. Eng., 136, 122 (2000).
- M. HALSALL, “CACTUS: A Characteristics Solution to the Neutron Transport Equations in Complicated Geometries,” AEEW-R-1291, Atomic Energy Establishment (1980).
- L. GOLDBERG, J. VUJIC, A. LEONARD, and R. STACHOWSKI, “The Characteristics Method in General Geometry,” Trans. Am. Nucl. Soc., 73, 173 (1995).
- M. ADAMS and E. LARSEN, “Fast Iterative Methods for Discrete-Ordinates Particle Transport Calculations,” Prog. Nucl. Energy, 40, 3 (2002).
- G. GRASSI, “A Non-Linear Spatial Multigrid Acceleration for the Method of Acceleration of the Characteristics in Unstructured Meshes,” Proc. Int. Topl. Mtg. Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications, Avignon, France, 2005.
- R. SANCHEZ, L. MAO, and S. SANTANDREA, “Treatment of Boundary Conditions in Trajectory-Based Deterministic Transport Methods,” Nucl. Sci. Eng., 140, 23 (2002).
- P. WESSELING, An Introduction to Multigrid Methods, John Wiley and Sons, Chichester, United Kingdom (1992).
- W. HACKBUSCH, Multi-Grid Methods and Applications, Springer-Verlag, Heidelberg, Germany (1985).
- K. SMITH and J. RHODES, “Full-Core, 2-D, LWR Core Calculations with CASMO-4E,” Proc. PHYSOR 2002, Seoul, Korea, 2002.
- K. KOEBKE, “A New Approach to Homogenization and Group Condensation,” IAEA-TECDOC, International Atomic Energy Agency, Vol. 231, p. 303 (1978).
- K. KOEBKE, “Advances in Homogenization and Dehomogenization,” Proc. Int. Topl. Mtg. Advances in Mathematical Methods for the Solution of Nuclear Engineering Problems, Munich, Germany, April 27–29, 1981, Vol. 2, p. 59 (1981).
- H. JOO, J. CHO, H. KIM, S. ZEE, and M. CHANG, “Dynamic Implementation of the Equivalence Theory in the Heterogeneous Whole Core Transport Calculation,” PHYSOR 2002, Seoul, Korea, 2002.
- S. NAKAMURA, Computational Methods in Engineering and Science, John Wiley and Sons, New York (1977).
- E. WACHSPRESS, Iterative Solutions of Elliptic Systems and Applications to the Neutron Diffusion Equations of Reactor Physics, Prentice-Hall, Inc., Englewood Cliffs, New Jersey (1966).
- “Physics of Plutonium Recycling. Vol. VII,” in “BWR MOX Benchmark Specifications and Results,” L’Agence pour L’Energie Nucléaire/Nuclear Energy Agency (AEN-NEA) (2003).
- A. AGGERY and L. BUIRON, “Etude du Benchmark d’un assemblage REB de type MOX Atrium 10,” Internal note.
- A. LEONARD and C. T. McDANIEL, “Optimal Polar Angles and Weights for the Characteristics Method,” Trans. Am. Nucl. Soc., 73, 172 (1995).
- “Expert Group on 3-D Radiation Transport Benchmarks, Benchmark Specification for 2-D/3-D MOX Fuel Assembly Transport Calculations Without Spatial Homogenization (C5G7MOX),” L’Agence pour L’Energie Nucléaire/Nuclear Energy Agency (AEN-NEA) (2001).
- S. SANTANDREA and R. SANCHEZ, “Acceleration Technique for the Method of Characteristics in Unstructured Meshes,” Ann. Nucl. Energy, 29, 323 (2002).
- S. SANTANDREA, Personal Communication.