Three-dimensional numerical model of neutron flux in hex-Z geometry

Hanuš, Milan, et al. "Three-dimensional numerical model of neutron flux in hex-Z geometry." Programs and Algorithms of Numerical Mathematics. Prague: Institute of Mathematics AS CR, 2008. 83-90. <http://eudml.org/doc/271404>.

@inProceedings{Hanuš2008,
abstract = {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 detailed computation of fluxes based on the transverse integrated diffusion equations. By this approach, it achieves a good balance between accuracy and speed.},
author = {Hanuš, Milan, Berka, Tomáš, Brandner, Marek, Kužel, Roman, Matas, Aleš},
booktitle = {Programs and Algorithms of Numerical Mathematics},
location = {Prague},
pages = {83-90},
publisher = {Institute of Mathematics AS CR},
title = {Three-dimensional numerical model of neutron flux in hex-Z geometry},
url = {http://eudml.org/doc/271404},
year = {2008},
}

TY - CLSWK
AU - Hanuš, Milan
AU - Berka, Tomáš
AU - Brandner, Marek
AU - Kužel, Roman
AU - Matas, Aleš
TI - Three-dimensional numerical model of neutron flux in hex-Z geometry
T2 - Programs and Algorithms of Numerical Mathematics
PY - 2008
CY - Prague
PB - Institute of Mathematics AS CR
SP - 83
EP - 90
AB - 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 detailed computation of fluxes based on the transverse integrated diffusion equations. By this approach, it achieves a good balance between accuracy and speed.
UR - http://eudml.org/doc/271404
ER -