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

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)
Authors:
 [1]
  1. Idaho National Laboratory, 2525 Fremont Avenue, Idaho Falls, ID 83415 (United States)
Publication Date:
OSTI Identifier:
22212905
Resource Type:
Conference
Resource Relation:
Conference: M and C 2013: 2013 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, Sun Valley, ID (United States), 5-9 May 2013; Other Information: Country of input: France; 20 refs.; Related Information: In: Proceedings of the 2013 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering - M and C 2013| 3016 p.
Publisher:
American Nuclear Society - ANS; La Grange Park (United States)
Research Org:
American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
Country of Publication:
United States
Language:
English
Subject:
97 MATHEMATICAL METHODS 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