References
- Abu‐Shumays , I. K. 1977 . Compatible product angular quadrature for neutron transport in x–y geometry . Nucl. Sci. Eng. , 64 : 299 – 316 .
- Gheorghiu , H. N. M. and Rahnema , F. 1998 . Variational principles for steady‐state neutron flux functionals . Trans. Th. Stat. Phys. , 27 : 67 – 95 .
- Ilas , D. and Rahnema , F. 2003 . A heterogeneous coarse mesh transport method . Trans. Th. Stat. Phys. , 32 : 441 – 467 .
- Lawrence , R. D. 1986 . Progress in nodal methods for the solution of the neutron diffusion and transport equations . Progr. Nucl. Energ. , 17 : 271 – 301 .
- Lewis , E. E. and Miller , W. F. Jr. 1984 . Computational Methods of Neutron Transport La Grange Park, IL : American Nuclear Society .
- Moriwaki , M. , Ishii , K. , Maruyama , H. and Aoyama , M. 1999 . A new direct calculation method of response matrices using a Monte Carlo calculation . J. Nuc. Sci. Tech. , 36 : 877 – 887 .
- Mosher , S. W. and Rahnema , F. An intra‐nodal flux expansion for a heterogeneous coarse mesh discrete ordinates method . Proceedings of the Conference on Nuclear Mathematical and Computational Sciences . April 6–10 , Gatlinburg, Tennessee.
- Neuman , C. P. and Schonbach , D. I. 1974 . Discrete (Legendre) orthogonal polynomials: A survey . Int. J. Numer. Meth. Eng. , 8 : 743 – 770 .
- Rathkopf , J. A. and Martin , W. R. 1986 . The finite element response matrix method for the solution of the neutron transport equation . Progr. Nucl. Energ. , 17 : 303 – 335 .
- Smith , K. S. 1986 . Assembly homogenization techniques for light water reactor analysis . Progr. Nucl. Energ. , 18 : 237 – 250 .
- Villarino , E. A. and Stamm'ler , R. J. J. 1984 . The heterogeneous response method in slab geometry . Ann. Nucl. Energ. , 11 : 429 – 440 .
- Volterra , V. 1959 . Theory of Functionals and of Integral and Integro‐Differential Equations New York : Dover .