Neutron-induced fission cross-sections of minor actinides have been measured at the white neutron source n_TOF at CERN, Geneva. The studied isotopes include U-233, interesting for Th/U based nuclear fuel cycles, Am-241,Am-243 and Cm-245, relevant for transmutation and waste reduction studies in new generation fast reactors (Gen-IV) or Accelerator Driven Systems.
The measurements take advantage of the unique features of the n_TOF facility, namely the wide energy range, the high instantaneous neutron flux and the low background. Results for the involved isotopes are reported from similar to 30 meV to around 1 MeV neutron enegy.
The measurements have been performed with a dedicated Fission Ionization Chamber (FIC), relative to the standard cross-section of the U-235 fission reaction, measured simultaneously with the same detector. Results are here reported.