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A Semianalytic Solution of the Monoenergetic Transport Equation in Cylindrical Geometry and the Derivation of Fluxes from Singular Sources

J. K. Fletcher

Nuclear Science and Engineering / Volume 85 / Number 1 / Pages 55-61

September 1983

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The neutron flux Φ(r,) at position r in the direction of unit vector is expanded as a series of the form with , the associated Legendre polynomial of order l,m. Variables θ and are the angles defining and N, an arbitrary odd number. Equations obtained for have solutions involving linear combinations of Bessel functions of the first and second kind. Expressions for the fluxes from point, line, and plane sources are found using a Green's function technique.

 
 
 
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