Nonlinear diffusion acceleration for the multigroup transport equation discretized with S{sub N} and continuous FEM with rattlesnake

Conference · Mon Jul 01 04:00:00 EDT 2013

OSTI ID:22212905

Wang, Y. ^[1]

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1. Idaho National Laboratory, 2525 Fremont Avenue, Idaho Falls, ID 83415 (United States)

Nonlinear diffusion acceleration (NDA) can improve the performance of a neutron transport solver significantly especially for the multigroup eigenvalue problems. The high-order transport equation and the transport-corrected low-order diffusion equation form a nonlinear system in NDA, which can be solved via a Picard iteration. The consistency of the correction of the low-order equation is important to ensure the stabilization and effectiveness of the iteration. It also makes the low-order equation preserve the scalar flux of the high-order equation. In this paper, the consistent correction for a particular discretization scheme, self-adjoint angular flux (SAAF) formulation with discrete ordinates method (S{sub N}) and continuous finite element method (CFEM) is proposed for the multigroup neutron transport equation. Equations with the anisotropic scatterings and a void treatment are included. The Picard iteration with this scheme has been implemented and tested with RattleS{sub N}ake, a MOOSE-based application at INL. Convergence results are presented. (authors)

• Research Organization: American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
• OSTI ID: 22212905
• Country of Publication: United States
• Language: English

Related Subjects

97 MATHEMATICS AND COMPUTING
ACCELERATION
ANISOTROPY
CORRECTIONS
DIFFUSION EQUATIONS
DISCRETE ORDINATE METHOD
EIGENFUNCTIONS
EIGENVALUES
FINITE ELEMENT METHOD
ITERATIVE METHODS
NEUTRON FLUX
NEUTRON TRANSPORT
NEUTRON TRANSPORT THEORY
NONLINEAR PROBLEMS
SCATTERING
STABILIZATION