الفهرس 
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Abstract
The continued assurance of the safety and integrity of muclear reactor components requires good under standing of the changes in material properties of such componantes as a function of radiation.in this respect, high accuracy and precision quantities are needed to relat the material effect occuring in the reactor cor under radiation and to be used to validate the calculational methodology. In part, studies are essential on neutron fields and neutron population in different reactor core configurations to support the requirements of reactor core analysis and its safe operation.
It is well known that, the fuel cell lattices are the most likely to be encountered in reactor design. Hence, informations about the neutron energy spectra in fuel cells are of primary importance for valuable study of heterogeneous systems. Study is deing considered of the detailed features of space-energy-depondence of thermal noutron spectra.
In this thesis, a study of the thermal neutron spectrum in fuel lattices and its potentiality in muclear reactor analysis is presented. The Boltzmann trasport equation was converted into aset of coupled differential equations which were solved numerically.