LTCalcoli has developed expertise in simulating neutron flux and its effects in nuclear systems for fusion or fission, particularly through the use of Monte Carlo codes.

Starting from geometry and neutron source inputs, the analyses allow obtaining information regarding various parameters such as:

• The neutron flux spectrum
• The spatial distribution of the neutron flux
• The generation of secondary radiation
• The dissipated energy
• Neutron multiplication

These parameters are applied either to the design of nuclear systems or to the verification of components exposed to neutron flux (material damage, DPA).

The results obtained can be used for subsequent nuclear inventory analyses or as input for thermal or thermo-mechanical analyses.