“…Neutron transport simulations combined with inventory calculations, with codes such as MCNP [1] and FISPACT [2], respectively, can produce the necessary quantitative predictions, but the reliability of these is largely dependent on the quality of the nuclear reaction cross section data. In most cases, nuclear reaction data, in a database such as the European Activation File (EAF) [3], is either largely or entirely based on theoretical calculations due to a lack of experimental data.…”