CALCULATION OF DEEP BURNUP OF NUCLEAR FUEL IN LATTICES WITH A REGULATABLE NEUTRON SPECTRUM

摘要

A method of calculating the burnup of nuclear fuel in breeding media with a regulatable neutron spectrum is described. Application of the method of small perturbations in the two-group approximation made it possible to supplement the system of equations for the variation of the nuclide composition of the fuel by an equation describing the variation of the spectrum hardness during fuel burnup, for which a prescribed criticality level is maintained. The results obtained are used as a basis for developing an algorithm for determining the breeding properties of a system with a regulatable neutron spectrum and its dynamical characteristics during fuel burnup.