Upper Limits of Accelerator-Driven Systems with Breeder Materials

摘要

In a real assembly, these values will be significantly lower depending on the neutron absorption in the structure, in the coolant and on the neutron leakage. On the other hand, system criticality, and consequently fission energy multiplication remains relatively modest for natural uranium (k_∞ = 0.816; M = 5.45) and depleted uranium (k_∞ = 0.752; M = 4.03). It is very low thorium (k_∞ = 0.40; M = 1.67). Please note, these calculations have been carried out for 100 % fissionable materials. In a real assembly with limited dimensions, and in the presence of coolant and structural materials, these values will be significantly lower. Hence exagerated expectations with respect to multiplication potential of the ADS must fail with natural breeder materials. Whereas, putting the emphasis on fissile fuel production with proper target and blanket design looks very promising. On the other hand, with the accumulation of the fission fuels, energy multiplication will increase. Time evolution of ADS blankets will be subject of different studies in future.