Three-stage fuel option for VVER-1200 reactor

Neutronic and burnup characteristics of potential dual‐cooled annular ( Th‐ 233 U‐ 235 U ) O 2 fuel for the advanced pressurized water reactors: An assembly‐level analysis

“…According to relevant studies, (Th‐ 233 U)O 2 fuel is a practical combination capable of self‐sustaining breeding in the thermal spectrum 3,20,21 . The fissile U‐233 can be created in a reactor or accelerator by bombarding Th‐232 and then recovered from irradiated thorium via chemical separation in a nuclear reprocessing facility.…”

“…18,19 According to relevant studies, (Th-233 U)O 2 fuel is a practical combination capable of self-sustaining breeding in the thermal spectrum. 3,20,21 The fissile U-233 can be created in a reactor or accelerator by bombarding Th-232 and then recovered from irradiated thorium via chemical separation in a nuclear reprocessing facility. U-233 generates enough neutrons per thermal neutron (the number of fission neutrons released per neutron absorbed, Table 1) to equal or exceed its consumption.…”