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Nodal adjoint method for multigroup diffusion in heterogeneous slab reactors
Author(s) -
Haidar Nassar H. S.
Publication year - 1992
Publication title -
numerical methods for partial differential equations
Language(s) - English
Resource type - Journals
SCImago Journal Rank - 0.901
H-Index - 61
eISSN - 1098-2426
pISSN - 0749-159X
DOI - 10.1002/num.1690080603
Subject(s) - eigenvalues and eigenvectors , mathematics , modified nodal analysis , nodal , slab , boundary value problem , neutron transport , finite element method , mathematical analysis , neutron , physics , nuclear physics , medicine , quantum mechanics , anatomy , thermodynamics , geophysics
A variational adjoint nodal method is proposed to yield an approximation theory for the eigenvalues of the multigroup neutron diffusion boundary value problem of a heterogeneous quasicritical one‐dimensional slab reactor. Semianalytical eigensolutions are constructed for the associated whole‐reactor group nodal fluxes. The method appears to be mathematically more consistent, computationally more straightforward, and practically more convenient than alternative nodal or finite element schemes. © 1992 John Wiley & Sons, Inc.