Fuel Cycles in Two-Region Homogeneous Reactor

The ways of converting a two-region aqueous homogeneous reactor fueled with 20% U235 enriched uranium into a U233 breeder are discussed. Numerical solutions are obtained for the burn-up equations combined with a one- group criticality condition and constant total power out-put. The "batch method" and the "continuous method" are compared. Time-dependent changes in the concentrations of individual isotopes, the number of uranium isotopes supplied to the core and removed from the blanket, the chemical processing rate, the ratio of the power produced in the blanket to that in the core, and the effect of U233 concentration in the blanket on these quantities are discussed for both cases.