الفهرس 
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Abstract
In the scope of constructing a complete set of codes calculating cell and reactor parameters in any type of reactors, ore. has to write a set of codes solving the tran¬sport equation for hetrog6neous cell of nuclear reactors
and a set of programmes solving problems of heterogenity
This later one is the aim of this thesis. A complete 3orapute%_-, code is written in Fortran langu¬age to calculate the neutron flux distribution and critica¬lity conditions inside a bare or reflected reactor with and without control rods.