Infinite-Medium Solutions of the Transport Equation, SN Discretization Schemes, and the Diffusion Approximation

Transport Theory and Statistical Physics

Volumn 32, Issue 5-7, 2003, Pages 623-643

  Larsen, Edward W ^a  

^a UNIVERSITY OF MICHIGAN   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

EID: 0242720002     PISSN: 00411450     EISSN: None     Source Type: Journal    
DOI: 10.1081/TT-120025069     Document Type: Conference Paper

References (18)

1. Adams, M. L. (2001). Discontinuous finite element transport solutions in thick diffusive problems. Nucl. Sci. Eng. 137:298.
2. Adams, M. L., Wareing, T. A., Walters, W. A. (1998). Characteristic methods in thick diffusive problems. Nucl. Sci. Eng. 130:18.
3. Alcouffe, R. E., Larsen, E. W., Miller, W. F. Jr., Wienke, B.R. (1978). Computational efficiency of numerical methods for the multigroup, Discrete-Ordinates Neutron Transport Equations: the Slab Geometry Case. Nucl. Sci. Eng. 71:111.
4. Case, K. M., Zweifel, P. F. (1967). Appendix F. In: Linear Transport Theory. Reading, Massachusetts: Addison-Wesley, pp. 296-298.
5. Hong, S. G. Cho, N. Z. (1998). CRX: A code for rectangular and hexagonal lattices based on the method of characteristics. Ann. Nucl. Energy 25:547.
6. Kershaw, D. S. (1981). Differencing of the diffusion equation in Lagrangian hydrodynamics codes. J. Comp. Phys. 39:375.
7. Knott et al., D. (1995). CASMO-4 Methodology Manual, STUDSVIK/SOA-95/02, Studsvik of America.
8. Larsen, E. W. (1983). On numerical solutions of transport problems in the diffusion limit. Nucl. Sci. Eng. 83:90.
9. Larsen, E. W. (1992), The asymptotic diffusion limit of discretized transport problems. Nucl. Sci. Eng. 112:336.
10. N schemes, linear infinite-medium solutions, and the diffusion approximation. Trans. Am. Nucl. Soc. 84:51.
11. Larsen, E. W. (2001b). Infinite medium solutions of the transport equation, discretization schemes, and the diffusion approximation; In: Proc. ANS Topical Meeting: International Conference on Mathematical Methods to Nuclear Applications, September 9-13, Salt Lake City, Utah, CD-ROM (ISBN: 0-89448-661-6, ANS Order No. 700286) available from the American Nuclear Society, 555 N. Kensington Avenue, La Grange Park, IL 60525.
12. Larsen, E. W., Morel, J. E., Miller, W. F. Jr. (1987). Asymptotic solutions of numerical transport problems in optically thick, diffusive regimes. J. Comp. Phys. 69:283.
13. Lewis, E. E., Miller, W. F. Jr. (1984). Computational Methods of Neutron Transport. New York: Wiley-Interscience.
14. Morel, J. E., Dendy, J. E., Hall, M. L., White, S. W. (1992). A cell-centered Lagrangian-mesh diffusion differencing scheme. J. Comp. Phys. 103:286.
15. Morel, J. E., Montry, G. R. (1984). Analysis and elimination of the discrete ordinales flux dip. Transport Theory Statist. Phys. 23:615.
16. Morel, J. E., Roberts, R. M., Shashkov, M. J. (1998). A local support-operators diffusion discretization scheme for quadrilateral r-z meshes. J. Comp. Phys. 144:17.
17. Palmer, T. S. (2001). Differencing the diffusion equation on unstructured polygonal meshes in two dimensions. Ann. Nucl. Energy 28:1851.
18. N methods on 3-D unstructured grids; In: Proc. Int. Conf. on Mathematics and Computation, Reactor Physics and Environmental Analysis in Nuclear Applications, Madrid, Spain, Sept. 27-30, 2:1185.