A Numerical Method for Solving the Neutron Transport Equation in Finite Cylindrical Geometry

概要

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A method is presented which provides a numerical solution to the steady state, energy dependent neutron transport equation for finite cylindrical geometry, with anisotropic treatment of elastic scattering and isotropic treatment of inelastic scattering. The main characteristic features of the method are the use of quasi-cartesian coordinates and the application of discrete ordinate numerical integration. A difference form of the Boltzmann equation is derived as the final expression for machine computation.<BR>Comparisons are given of the numerical solutions with an analytical solution for a constant source distribution, and with NIOBE calculations and experimental spectra for neutron transport in water, with good agreement obtained between them.
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