Diffusion synthetic methods for computational modeling of one-speed slab-geometry transport problems with linearly anisotropic scattering
- 1. Programa de Pós-Graduação em Ciências Computacionais, Instituto de Matemática e Estatística (IME), Universidade do Estado do Rio de Janeiro (UERJ), Rua São Francisco Xavier 524, 6, o, andar, 20550-013 Rio de Janeiro, RJ (Brazil)
- 2. Programa de Pós-Graduação em Modelagem Computacional, Instituto Politécnico (IPRJ), Universidade do Estado do Rio de Janeiro (UERJ) P.O. Box 97282, 28610-974 Nova Friburgo, RJ (Brazil)
Description
Highlights: • Analytical numerical methods. • Fixed-source SN transport problems. • Spectral nodal methods. • Diffusion synthetic methods. • Analytical angular reconstruction scheme within each region of a multilayer slab. - Abstract: Two diffusion synthetic methods are described for computational modeling of one-speed, slab-geometry transport problems with linearly anisotropic scattering. These methods are referred to as diffusion synthetic methods, since the lower-order diffusion is used to simplify numerical solutions to the higher-order transport equation. In part I of this paper the word simplify is used in the sense of reducing the number of iterations to a prescribed stopping criterion; in other words, in the sense of accelerating the iteration on the scattering source in discrete ordinates (SN) calculations, by generating an improved initial guess. In part II, the word simplify is used in the sense of generating numerical results for the angular flux by solving analytically the first-order form of the transport equation in slab geometry with diffusion approximation for the scattering source integral terms. As with these two offered synthetic methods, special approximate boundary conditions are used in the diffusion equation to account for prescribed incident flux on the outer boundaries of the slab, including vacuum boundary conditions. Numerical results are given to illustrate the application of these two synthetic methods.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.pnucene.2013.12.014Additional details
Identifiers
- DOI
- 10.1016/j.pnucene.2013.12.014;
- PII
- S0149197014000043;
Publishing Information
- Journal Title
- Progress in Nuclear Energy
- Journal Volume
- 73
- Journal Page Range
- p. 179-187
- ISSN
- 0149-1970
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 51011161
- Subject category
- S71: CLASSICAL AND QUANTUM MECHANICS, GENERAL PHYSICS; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- ANISOTROPY; BOUNDARY CONDITIONS; COMPUTERIZED SIMULATION; DIFFUSION EQUATIONS; DISCRETE ORDINATE METHOD; NEUTRON TRANSPORT; NUMERICAL SOLUTION; PHASE SPACE; SCATTERING; SLABS; TRANSPORT THEORY
- Descriptors DEC
- CALCULATION METHODS; DIFFERENTIAL EQUATIONS; EQUATIONS; MATHEMATICAL SOLUTIONS; MATHEMATICAL SPACE; NEUTRAL-PARTICLE TRANSPORT; PARTIAL DIFFERENTIAL EQUATIONS; RADIATION TRANSPORT; SIMULATION; SPACE
Optional Information
- Notes
- Copyright © 2014 Elsevier Ltd. All rights reserved.