References
- M. PILCH, “Measuring and Communicating Progress in Predictive Capability,” presented at The Computational Methods in Transport Workshop, Tahoe City, California, September 9–14, 2006.
- B. D. GANAPOL, “The Analytical Nuclear Engineering Benchmark Library,” NRRT-NE-9641 (Sep. 1998).
- K. M. CASE and P. F. ZWEIFEL, Linear Transport Theory, Addison-Wesley, New York (1967).
- G. J. MITSIS, “Transport Solutions to the Monoenergetic Critical Problems,” ANL-6787, Argonne National Laboratory (1963).
- R. M. WESTFALL and D. R. METCALF, “Singular Eigenfunction Solution of the Monoenergetic Neutron Transport Equation for Finite Radially Reflected Critical Cylinders,” Nucl. Sci. Eng., 52, 1 (1973).
- J. R. THOMAS, Jr., J. D. SOUTHERS, and C. E. SIEWERT, “The Critical Problem for an Infinite Cylinder,” Nucl. Sci. Eng., 84, 79 (1983).
- C. E. SIEWERT and J. R. THOMAS, Jr., “Neutron Transport Calculations in Cylindrical Geometry,” Nucl. Sci. Eng., 87, 107 (1984).
- R. SANCHEZ, “Generalization of Asaoka’s Method to Linearly Anisotropic Scattering: Benchmark Data in Cylindrical Geometry,” CEA-N-1831, CEN de Saclay, Gif-sur-Yvette, France (1975).
- S. ZHANG and J. JIN, Computation of Special Functions, John Wiley & Sons, New York (1996).
- K. M. CASE et al., “Introduction to the Theory of Neutron Diffusion,” Vol. 1, Los Alamos Scientific Laboratory Report (1953).
- W. H. PRESS et al., Numerical Recipes, Cambridge University Press, New York (1992).
- G. BAKER and P. GRAVES-MORRIS, Padé Approximants, Cambridge University Press, New York (1996).