Abstract
Alternative analytical solutions of the neutron diffusion equation for both infinite and finite cylinders of fissile material are formulated using the homotopy perturbation method. Zero flux boundary conditions are investigated on boundary as well as on extrapolated boundary. Numerical results are provided for one-speed fast neutrons in 235U. The results reveal that the homotopy perturbation method provides an accurate alternative to the Bessel function based solutions for these geometries.
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