DEPLETION AND INVENTORY CALCULATION FOR THE NEW FUEL OF IEN'S ARGONAUTA REACTOR

Resumo

This work presents fuel depletion simulations calculated for the Argonauta research reactor. Using
the Monte Carlo N-Particle (MCNP 1.0) code and a developed reactor’s model as a basis, the principal
methodology of this work consisted of hypothetical burning scenarios using the new U 3 Si 2 -Al reactor’s
fuel. The found masses in the inventory for the highlighted isotopes can be relevant for license
procedures for U3Si2 fuel and for studying emergency scenarios and hypothetical accidents at the
facility.