The neutron flux is a crucial parameter for the analysis of nuclear reactors, because it affects
the reaction rate and thus the fuel burnup. Moreover, a very precise knowledge of the flux in
the irradiation positions is helpful for benchmarking the simulation models of the reactor. In
particular, an MCNP model of the TRIGA Mark II reactor installed at LENA (Laboratory of
Applied Nuclear Energy) of the University of Pavia was developed in the recent years,
describing the geometries and the materials of the whole reactor with very good accuracy. In …