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Approximate Solution to Neutron Transport Equation with Linear Anisotropic Scattering
Abstract:A method to obtain an approximate solution to the transport equation, when both sources and collisions show a linearly anisotropic behavior, is outlined and the possible implications for numerical calculations in applied neutronics as well as shielding evaluations are investigated.

The form of the differential system of equations taken by the method is quite handy and looks simpler and more manageable than any other today available technique. To go deeper into the efficiency of the method, some typical calculations concerning critical dimensions of multiplying systems are then performed and the results are compared with the ones coming from the classical SN approximations. The outcome of such calculations leads us to think of interesting developments of the method which could be quite useful in alternative to other today widespread approximate procedures, for any geometry, but especially for curved ones.
Keywords:neutron transport theory  multiplying systems  linear anisotropic scattering  efficiency  transport equation  numerical calculations  criticality
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