The implementation of program packing of two codes is described: LAHET (LANL, USA) and REACTOR (KIAM, RF). The module permitting from files with results of LAHET’s calculation to create a neutron-source (spallation) and to record him in an input file for further calculation over the program the REACTOR is developed. It is shown, that the detail count of source distribution over space increases accuracy of calculation of the main physical values: a neutron multiplication factor of a blanket, coefficient of irregularity of energy release etc. The feature of neutron - physical calculation of hybrid system (target + blanket) is a slow convergence of iterative algorithms for solving the system of diffusive equations with an external source. For acceleration it is suggested to use trinomial universal algorithms of Chebyshev of 2 kind. The efficiency of such method of acceleration is demonstrated on results of calculation of IAEA test. The optimum length of a cycle is obtained.

Mathematical modelling in actual problems of science and technics