The effects of 232U and 236U on uranium recycling in boiling water reactors are studied with the two-dimensional lattice physics code TGBLA. A simple analytic expression is proposed for reactivity compensation factor K, taking into account the self-shielding effect of resonance absorption in 236U: K = a + b/ (1 + ce6)1/2, where e6 denotes the 236U concentration. To output the same energy as the 3.0 wt% enrichment fuel free from 236U, the constants are determined to be a = 0.06, b = 0.23, and c = 1.9. The introduction of 1 ppb 232U increases the surface dose rate of the fuel assembly by 60% over the aged enriched natural uranium. Lead time is as important as cooling time in 232U production because of the presence of the chain that originates from the alpha decay of naturally occurring 234U. The natural uranium feed and the separative work requirement are evaluated on these bases, introducing typical recycling strategies, and it appears that uranium recycling saves 17 to 19% of the natural uranium but increases the separative work by 0 to 2%. The front-end cost analysis reveals the benefit of a concentrated utilization of reprocessed uranium, which results from the self-shielding effect of 236U and the assumption of a linear dependence of the front-end penalty on 232U concentration. Also studied are plutonium composition in irradiated fuels and the effects of extended burnup.