الفهرس 
Review of Neutron ThermalizationOnly 14 pages are availabe for public view
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Abstract
Neutron thermalization problem in reactor cells
always been of fun”:’arJental importance for the phys ice caloulo.tions in thermo.l reactors design.
The thermal neutron ~istribution, in space o.n~ energy, in reactor lattices is of an interest because of its importance in calculation of important quantities
like thermal neutron interaction rates, disadvantage factors a~ other impQrtant parameters.
In this thesis one solves the integral-transport equation for the thermal neutron flux G.istribution arising from a known epithermal flux in one ~imensional cyline¬drical geometry, using the computer pro3ramme (TBERUOS) maG.e by IIoneck (la), cm”:’ ac.opting the approach made by
I. Carlvik (8) for calculating the transport kernels
using white boun”:’ary conuitions.
The ac.option of Carlvik’s approach refrains one
from the approxioations introliuced by lIoneck, and also facilitates the calculations of the collision probabilities to obtain the transport kernels useJ. to solve the trans¬port equation.