الفهرس 
Methods of solving the transport equationOnly 14 pages are availabe for public view
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Abstract
A developed method for solving the one-speed neutron integral transport equation for isotropic scattering in a finite slab geometry is investigated. The direct solution of the integral transport equation gives the stationary
neutron flux. Knowing the stationary flux, the reflection or the transmission angular distributions, the reflection and the transmission coefficients could be obtained .
A developed method for solving the one-speed neutron integral transport equation for isotropic scattering in a finite slab geometry is investigated. The direct solution of the integral transport equation gives the stationary
neutron flux. Knowing the stationary flux, the reflection or the transmission angular distributions, the reflection and the transmission coefficients could be obtained .
A developed method for solving the one-speed neutron integral transport equation for isotropic scattering in a finite slab geometry is investigated. The direct solution of the integral transport equation gives the stationary
neutron flux. Knowing the stationary flux, the reflection or the transmission angular distributions, the reflection and the transmission coefficients could be obtained .
The developed method is based on expanding the kernel of the integral transport equation which takes the form of onential integral function in a Fourier series.