Specific features of reactor kinetics with fissile isotope nonuniform distribution

Transients in the VG-400 reactor at zero power level specific for control and safety tasks under fissile isotope nonuniform distribution, are considered. Dynamic errors in estimating the transients for integral neutron flux density and reactor reactivity, are determined. The conclusion is made that characteristics of delayed neutrons for all fissile isotopes should be taken into acount in multi- and few-group approximations, when solving the control and safety tasks for the reactor with high fuel burnups and especially under component nonuniform distribution