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Mixed-Hybrid Transport Discretization Using Even and Odd PN Expansions

S. Van Criekingen, E. E. Lewis, R. Beauwens

Nuclear Science and Engineering / Volume 152 / Number 2 / Pages 149-163

February 2006

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A mixed-hybrid treatment of the spatial variables of the within-group neutron transport equation generalizes existing mixed and hybrid methods, combining their attractive features: the simultaneous approximation of even- and odd-parity angular flux components and the use of Lagrange multipliers to enforce interface continuity. A finite element spatial discretization and spherical harmonic angular expansions are used. We discuss rank conditions for the proposed methods and provide a new derivation of the Rumyantsev interface conditions. Even- and odd-parity interface continuity properties corresponding to these Rumyantsev conditions are established. We examine inclusion conditions and the interaction of the primal/dual distinction due to the spatial variable with the even/odd-order spherical harmonic approximation distinction due to the angular variable. Numerical solutions for both even- and odd-order spherical harmonic approximations are presented, and a promising enclosing property is observed in our results.

 
 
 
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