Comparison of several methods of calculating neutron flux in a nuclear reactor channel

The neutron flux in technological channels of RBMK type reactors has been calculated in the one-speed approximation by the following methods: the surface pseudosources method (SPM) in G3-approximation with reducing the channel to a cylindrical geometry; the SPM in G31 - approximation; the first collision probability method (FCPM), the Monte Carlo method and the generalized FCPM. The methods are compared in terms of accuracy and computer calculation time, the results obtained by the Monte Carlo method being taken as reference ones. It is concluded, that the SPM with reducing the channel to a cylindrical geometry is superior in terms of calculating time and only slightly inferior to the SPM in G31 - approximation and to the generalized FSPM in accuracy