Investigation of the Self-Interrogation Neutron Resonance Densitometry applied to spent fuel using Monte Carlo simulations

We concluded that a better sensitivity is expected when the fuel assembly is in air, surrounded by a slab of polyethylene. The obtained results also indicated that the ratio between the neutron flux in the fast region and the neutron flux around the 0.3 eV resonance is more strongly related to the 239Pu content than other ratios. The impact of 235U on the SINRD signature was found to be significant, while limited effects were due to other nuclides.