An approximative method of solving the flat thermal neutron flux problem for an infinite cylindrical homogenized reactor fueled with natural uranium

A. Mjasnikov; R. Zezula

Acta Universitatis Carolinae. Mathematica et Physica (1972)

  • Volume: 013, Issue: 2, page 61-71
  • ISSN: 0001-7140

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Mjasnikov, A., and Zezula, R.. "An approximative method of solving the flat thermal neutron flux problem for an infinite cylindrical homogenized reactor fueled with natural uranium." Acta Universitatis Carolinae. Mathematica et Physica 013.2 (1972): 61-71. <http://eudml.org/doc/246748>.

@article{Mjasnikov1972,
author = {Mjasnikov, A., Zezula, R.},
journal = {Acta Universitatis Carolinae. Mathematica et Physica},
language = {eng},
number = {2},
pages = {61-71},
publisher = {Charles University in Prague},
title = {An approximative method of solving the flat thermal neutron flux problem for an infinite cylindrical homogenized reactor fueled with natural uranium},
url = {http://eudml.org/doc/246748},
volume = {013},
year = {1972},
}

TY - JOUR
AU - Mjasnikov, A.
AU - Zezula, R.
TI - An approximative method of solving the flat thermal neutron flux problem for an infinite cylindrical homogenized reactor fueled with natural uranium
JO - Acta Universitatis Carolinae. Mathematica et Physica
PY - 1972
PB - Charles University in Prague
VL - 013
IS - 2
SP - 61
EP - 71
LA - eng
UR - http://eudml.org/doc/246748
ER -

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