On eigendistributions in linear transport theory

1979 ◽  
Vol 83 (3-4) ◽  
pp. 303-326 ◽  
Author(s):  
C. G. Lekkerkerker
Keyword(s):  
Transport Theory ◽  
Neutron Transport ◽  
Full Range ◽  
Scattering Function ◽  
Neutron Transport Equation ◽  
One Dimensional ◽  
Factorization Problem ◽  
Linear Transport ◽  
The One ◽  
Linear Transport Theory

SynopsisAn attempt is made to provide a sound basis for the method of singular eigenfunction expansions which has been in vogue in linear transport theory for some decades. The procedure is exemplified by a treatment of the one-dimensional neutron transport equation with a degenerate scattering function. Full-range as well as half-range results are derived. At the end of the paper the implications for a certain matrix factorization problem are given.

About the FN Approximation to Fractional Neutron Transport Equation in Slab Geometry

2011 ◽  
Author(s):  
Dumitru Baleanu ◽  
Abdelouahab Kadem
Keyword(s):  
Transport Equation ◽  
Polynomial Approximation ◽  
Approximation Method ◽  
Legendre Polynomial ◽  
Neutron Transport ◽  
Neutron Transport Equation ◽  
Slab Geometry ◽  
One Dimensional ◽  
The One

The neutron transport denotes the study of the motions and interactions of neutrons with materials. In given applications we need to know where neutrons are in an apparatus, what direction they are moving, and how fast they are going. In this manuscript the Legendre polynomial approximation method FN was applied to the one dimensional slab geometry neutron transport equation.

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