Parallel solvers for the transient multigroup neutron diffusion equations

DOI<link itemprop=identifier href="https://doi.org/10.1002/(SICI)1097-0207(20000410)47:10<1751::AID-NME855>3.0.CO;2-4" /><1751::AID-NME855>3.0.CO;2-4 10.1002/(SICI)1097-0207(20000410)47:10<1751::AID-NME855>3.0.CO;2-4zbMath1078.82554OpenAlexW2085744775MaRDI QIDQ4494613

Robert Scheichl

Publication date: 30 January 2001

Full work available at URL: https://doi.org/10.1002/(sici)1097-0207(20000410)47:10<1751::aid-nme855>3.0.co;2-4

zbMATH Keywords

non-symmetric matricesmixed finite volume discretisationparallel Bi-CGStabparallel multi-gridtransient multigroup neutron diffusion equations

Mathematics Subject Classification ID

Finite element, Rayleigh-Ritz and Galerkin methods for boundary value problems involving PDEs (65N30) Parallel numerical computation (65Y05) Nuclear reactor theory; neutron transport (82D75)

Cites Work

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• Bi-CGSTAB: A Fast and Smoothly Converging Variant of Bi-CG for the Solution of Nonsymmetric Linear Systems
• On the relationship between nodal schemes and mixed‐hybrid finite elements
• Load Balancing for Adaptive Multigrid Methods

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