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.
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     author = {A. V. Shilkov},
     title = {Averaging of cross sections and spectrum in neutron transport},
     journal = {Matemati\v{c}eskoe modelirovanie},
     pages = {63--81},
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     number = {2},
     year = {1991},
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     url = {http://geodesic.mathdoc.fr/item/MM_1991_3_2_a4/}
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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/