Figure 3.31 shows the quantities of materials to be supplied or processed per year for a 1000-MWe LWR operated with recycle of uranium in spent fuel, after steady-state fuel-cycle conditions have been established. To generate electricity at this rate with a power-cycle thermal efficiency of 32.5 percent at a capacity factor of 80 percent requires that the reactor be supplied with 27,271 kg/уеаг of uranium enriched to 3.3 w/o 235U. This fuel is expected to support a bumup of 33,000 MWd/MT with three-zone fueling. Of the other material quantities shown in the flow sheet, the most significant are the following: 25,674 kg uranium containing 0.83 w/o 235 U is recovered in the form of UF6 and recycled to isotope separation. Uranium isotope separation is assumed to reject tails containing 0.3 w/o 23SU. Under these conditions the uranium isotope separation facility needs 168,090 kg/year of natural uranium feed in the form of UF6 and produces 106,974 separative work units per year (defined in Chap. 13). To provide UF6 at this rate requires an annual supply of 439,199 lb U308 in uranium ore concentrates. The fuel reprocessing plant produces 243.5 kg/уеаг of plutonium of the isotopic composition given at the right of Fig. 3.31.