%0 Journal Article
%A Mjasnikov, A.
%A Zezula, R.
%T An approximative method of solving the flat thermal neutron flux problem for an infinite cylindrical homogenized reactor fueled with natural uranium
%J Acta Universitatis Carolinae. Mathematica et Physica
%D 1972
%P 61-71
%V 13
%N 2
%I mathdoc
%U http://geodesic.mathdoc.fr/item/AUCMP_1972__13_2_a6/
%G en
%F AUCMP_1972__13_2_a6