Assessment of Sensitivity of Neutron-Physical Parameters of Fast Neutron Reactor to Purification of Reprocessed Fuel from Minor Actinides

摘要

The work is devoted to computational investigation of the dependence of basic physical parame- ters of fast neutron reactors on the degree of purification of plutonium from minor actinides obtained as a result of pyroelectrochemical reprocessing of spent nuclear fuel and used for manufacturing MOX fuel to be reloaded into the reactors mentioned. The investigations have shown that, in order to preserve such important parameters of a BN-800 type reactor as the criticality, the sodium void reactivity effect, the Doppler effect, and the efficiency of safety rods, it is possible to use the reprocessed fuel without separation of minor actinides for refueling (recharging) the core.