Numerical modeling of neutron flux in hexagonal geometry
Berka, Tomáš; Brandner, Marek; Hanuš, Milan; Kužel, Roman; Matas, Aleš — 2008
Programs and Algorithms of Numerical Mathematics
Numerical modeling of neutron flux in hexagonal geometry
Three-dimensional numerical model of neutron flux in hex-Z geometry
We present a method for solving the equations of neutron transport with discretized energetic dependence and angular dependence approximated by the diffusion theory. We are interested in the stationary solution that characterizes neutron fluxes within the nuclear reactor core in an equilibrium state. We work with the VVER-1000 type core with hexagonal fuel assembly lattice and use a nodal method for numerical solution. The method effectively combines a whole-core coarse mesh calculation with a more...
A short philosophical note on the origin of smoothed aggregations
We derive the smoothed aggregation two-level method from the variational objective to minimize the final error after finishing the entire iteration. This contrasts to a standard variational two-level method, where the coarse-grid correction vector is chosen to minimize the error after coarse-grid correction procedure, which represents merely an intermediate stage of computing. Thus, we enforce the global minimization of the error. The method with smoothed prolongator is thus interpreted as a qualitatively...
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