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...
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