233U Breeding in accelerator sub-critical fast reactor

Accelerator driven Sub-critical Fast Reactor (ADFR) is chosen as fissile material breeding reactor. (U Pu) O
x
is chosen as fuel in the core and ThO
2
as fertile material in the blanket zone to breed
²³³
U. Molten lead is chosen as coolant because of its better neutronic and chemical characteristics over sodium. The program system used for neutronics study consists of: LAHET, for the simulation of the interaction between the proton with medium energy and the nuclei of the target; MONP4A, for the simulation of neutron transport with energy below 20 MeV in the sub critical reactor; CONNECT1, for the processing of some tallies provided by the output of MCNP4A in order to prepare micro-cross sections for elements used for burnup calculation; ORIGEN2, used for multi-region burnup calculation; CONNECT2, for the processing of atom dens ties of some elements provided in the output of ORIGEN2 in order to prepare input to LAHET calculation for next time step. The calculated results show that the proposed case is feasible for breeding fissile material considering the criticality safety, power density, burnup, etc.