Belousov V.I., Boyarinov V.F., Davidenko V.D., Dyachkov I.I., Ioannisian M.V., Chernov K.G.
National Research Centre “Kurchatov Institute”, Moscow, Russia
The KIR program code for solving stationary and non-stationary neutron transport equations based on the analog Monte Carlo method in the group approximation is considered. The results of the verification stage of the group physical module MAGMA as part of the KIR program are presented. The international nonstationary numerical benchmark test C5G7-TD is used for verification, in which the energy region neutrons is divided into 7 energy groups neutrons, and the parameters of delayed neutrons are presented in the form of eight group constants. To check the results of the KIR program code, the results obtained by the SUHAM-2D-TD program are used. The results of exercises D0 and TD3 are presented, in which the transient process associated with the instantaneous insertion of the SUZ rods and changes in the density of the coolant, respectively, is modeled. The results of the verification stage of the KIR program with the MAGMA group module are summarized.
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