@article{AUCMP_1972__13_2_a6,
     author = {Mjasnikov, A. and Zezula, R.},
     title = {An approximative method of solving the flat thermal neutron flux problem for an infinite cylindrical homogenized reactor fueled with natural uranium},
     journal = {Acta Universitatis Carolinae. Mathematica et Physica},
     pages = {61--71},
     publisher = {mathdoc},
     volume = {13},
     number = {2},
     year = {1972},
     language = {en},
     url = {http://geodesic.mathdoc.fr/item/AUCMP_1972__13_2_a6/}
}