Development of a method of surface pseudo-sources for calculation of neutron fields in cells with a fuel rod bundle

A method of surface pseudo-sources to calculate neutron fields in complex two-dimensional heterogeneous units in a single-speed approximation is described. A system of equations in Gsub(N)sup(p) approximations has been obtained. Realization of the developed method of surface pseudo-sources for the calculation of neutron flux, averaged over zones, in the heterogeneous reactor channel has been achieved. From a comparison of the calculation results by the method of surface pseudo-sources and by the Monte Carlo method, if follows that the error of G31 approximation in the averaged neutron flux is not more than 1% (approximately 30 s calculation on the BESM6 computer). Calculations have shown that importance of taking into account the first axial harmonic of the distribution function of neutrons in fuel elements. The advantages of the method of surface pseudo-sources over the method of first collision probability have been elucidated