Complex reactor cell calculation by means of consecutive use of the one-dimensional algorithms based on the DSsub(n)-method

The technique for approximate calculation of the water cooled and moderated reactor cell based on using the DSn-method and the TESI-2S program for the BESM-6 computer in which the proposed technique is realized are described. The calculational technique is based on division of the reactor complex cell into simple one-dimensional cylindrical cells. Series of cells obtained that way is calculated beginning from the first one. After each cell calculation the macrocross sections are averaged over the cell vomome using the neutron spatial and energy distribution. The possibility of approximate account for neutron transport between the cells of the same rank by equating neutron fluxes on the cell boundary is supposed. The spatially and energy neutron flux distribution over cells is performed using the conditions of isotropic neutron reflection on the cell boundary. The results of the proposed technique approbation on the example of the ABV-1.5 reactor fuel assembly high accuracy and reliability of the employed algorithm