A Finite Element Method for the Neutron Transport Equation in an Infinite Cylindrical Domain

DOI10.1137/S0036142992238119zbMath0918.65092OpenAlexW2057996466MaRDI QIDQ4210280

Mohammad Asadzadeh

Publication date: 21 September 1998

Published in: SIAM Journal on Numerical Analysis (Search for Journal in Brave)

Full work available at URL: https://doi.org/10.1137/s0036142992238119

zbMATH Keywords

finite elementerror estimateBesov spacesconvergence ratespatial discretizationinterpolation spacesneutron transport equationcritical eigenvalueduality algorithmscalar flux

Mathematics Subject Classification ID

Numerical methods for integral equations (65R20) Integro-partial differential equations (45K05) Transport processes in time-dependent statistical mechanics (82C70)

Related Items (10)

Multigrid algorithms for solving multigroup neutron transport equations ⋮ Discontinuous Galerkin finite element method applied to the 1D spherical neutron transport equation ⋮ Note on the solution of transport equation by Tau method and Walsh functions ⋮ Modern Monte Carlo Variants for Uncertainty Quantification in Neutron Transport ⋮ Spatial approximation of the radiation transport equation using a subgrid-scale finite element method ⋮ Fast algorithms for integral formulations of steady-state radiative transfer equation ⋮ A fast algorithm for radiative transport in isotropic media ⋮ CONVERGENCE OF A DISCONTINUOUS GALERKIN SCHEME FOR THE NEUTRON TRANSPORT ⋮ AN OPTIMALITY CONDITION FOR THE ASSEMBLY DISTRIBUTION IN A NUCLEAR REACTOR ⋮ An adaptive nested source term iteration for radiative transfer equations

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