Nuclear Science and Engineering / Volume 51 / Number 1 / May 1973 / Pages 76-78
Technical Note / dx.doi.org/10.13182/NSE73-A23259
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A general multidirectional modal representation for the angular density of the one-speed neutron transport equation is discussed. The properties of orthogonality and recurrence are presented together with expressions for several neutranic parameters. The system of equations for the spatial moments are established and certain features described. It is shown that some known solution formulations are special cases of this more general representation.