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Symmetrized Neutron Transport Equation and the Fast Fourier Transform Method

Nguyen Quang Sinh, Jan Kisyński, Janusz Mika

Nuclear Science and Engineering / Volume 67 / Number 3 / September 1978 / Pages 363-370

Technical Note / dx.doi.org/10.13182/NSE78-A27261

The differential equation obtained from the neutron transport equation by the application of the source iteration method in two-dimensional rectangular geometry is transformed into a symmetrized form with respect to one of the angular variables. The discretization of the symmetrized equation leads to finite difference equations based on the five-point scheme and solved by use of the fast Fourier transform method. Possible advantages of the present approach are shown on test calculations.