A complex approach based on the consistent modeling of neutron-physics processes and processes of cascade separation of isotopes is applied for analyzing physical problems of the multiple usage of reprocessed uranium in the fuel cycle of light water reactors. A number of scenarios of multiple recycling of reprocessed uranium in light water reactors are considered. In the process, an excess absorption of neutrons by the 236 U isotope is compensated by re-enrichment in the 235 U isotope. Specific consumptions of natural uranium for re-enrichment of the reprocessed uranium depending on the content of the 232 U isotope are obtained.