A trigonal nodal solution approach to the multi-group simplified P3 equations in the reactor code DYN3D
A trigonal nodal solution approach to the multi-group simplified P3 equations in the reactor code DYN3D
Duerigen, S.; Grundmann, U.; Mittag, S.; Merk, B.; Fridman, E.; Kliem, S.
The neutronics model of the nodal reactor dynamics codeDYN3D developed for 3-D analyses of steady states and transients in light-water reactors has been extended by a simplified P3 (SP3) neutron transport option to overcome the limitations of the diffusion approach. To provide a method being applicable to reactors with hexagonal fuel assemblies and furthermore allowing flexible mesh refinement, the nodal SP3 method has been developed on the basis of a flux expansion in trigonal-z geometry. In this paper, the derivation of the trigonal SP_3 method is presented and preliminary assessment of the methodology is performed.
Keywords: simplified P3; SP3; nodal method; trigonal; triangular; hexagonal
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Contribution to proceedings
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2011), 08.-12.05.2011, Rio de Janeiro, Brazil, 978-85-63688-00-2 -
Lecture (Conference)
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2011), 08.-12.05.2011, Rio de Janeiro, Brazil
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