Averaging of cross sections and spectrum in neutron transport
Matematičeskoe modelirovanie, Tome 3 (1991) no. 2, pp. 63-81
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Transport equation averaging methods are developed: generalized multigroup approximation and averaging over Lebesgue's sets. These methods permit to calculate numerous resonances in neutron cross sections and spectrum economically and with sufficient accuracy.
@article{MM_1991_3_2_a4,
author = {A. V. Shilkov},
title = {Averaging of cross sections and spectrum in neutron transport},
journal = {Matemati\v{c}eskoe modelirovanie},
pages = {63--81},
year = {1991},
volume = {3},
number = {2},
language = {ru},
url = {http://geodesic.mathdoc.fr/item/MM_1991_3_2_a4/}
}
A. V. Shilkov. Averaging of cross sections and spectrum in neutron transport. Matematičeskoe modelirovanie, Tome 3 (1991) no. 2, pp. 63-81. http://geodesic.mathdoc.fr/item/MM_1991_3_2_a4/