Model with psychometric quality for safety culture assessment in nuclear facilit...

Human error probability quantification using fuzzy methodology in nuclear plants

Development of a model for dimensioning the production capacity of nuclear fuel factories...

Measurement studies by the Monte Carlo method for total body irradiation

Neutronic and thermal-hydraulic analysis of a device for irradiation of LEU UAlx-Al...

Experimental determination of espectral ratios and of neutrons energy flux in the...

Analysis of corrective and predictive maintenance data for the pump set in the primary...

Seismic Probabilistic Safety Assessment: regulatory requirements, current guidelines,...

Solução analítica da cinética espacial do modelo de difusão para sistemas homogêneos...

Development of analytical and numerical models associated to the condensation phenomenon...