Characterization and qualification of a measurement station for neutron assay of burnt fuel

The characterization of spent fuel is of interest to the nuclear industry for in- and out- core applications such as core design, spent fuel storage and transportation. The usual approach relies on the measurement of the gamma-ray emission of burnt fuel. The measurement of the neutron intrinsic source, together with knowledge of the cooling time and initial enrichment of the fuel, could be another approach to measure the burnup of spent fuel. (orig.)