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Title: An approximative method of solving the flat thermal neutron flux problem for an infinite cylindrical homogenized reactor fueled with natural uranium (English)
Author: Mjasnikov, A.
Author: Zezula, R.
Language: English
Journal: Acta Universitatis Carolinae. Mathematica et Physica
ISSN: 0001-7140
Volume: 13
Issue: 2
Year: 1972
Pages: 61-71
Category: math
Date available: 2012-10-05T18:25:31Z
Last updated: 2012-10-05
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