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Acta Universitatis Carolinae. Mathematica et Physica
Volume 13
Author: Mjasnikov, A.
Mjasnikov, A.; Zezula, R.
:
An approximative method of solving the flat thermal neutron flux problem for an infinite cylindrical homogenized reactor fueled with natural uranium
.
(English).
Acta Universitatis Carolinae. Mathematica et Physica
,
vol. 13 (1972), issue 2
,
pp. 61-71
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