[en] A few-group diffusion program for the calculation of subcritical reactor with external local neutron source is presented. Algorithm put in the basis of heterogeneous problem solution is discussed. The possibility to simulate the method of reverse multiplication using the program is presented in detail. Calculations are made to determine core efficiency in a subcritical reactor. The calculations are compared with experimental results
Original Title
Raschetnoe opredelenie ehffektivnosti sterzhnya v podkriticheskom reaktore s lokal'nym vneshnim istochnikom metodom obratnogo umnozheniya