Sensitivity analisys in nuclear fuel performance codes

Modeling of PWR fuel at extended burnup

Neutronic and thermal-hydraulic analysis of devices for irradiation of LEU targets...

Neutronic, thermal-hydraulics and accident analysis calculations of an miniplate...

Study on the economic feasibility for the implementation of the SMART nuclear reactor...

Three-dimensional mechanical and dynamic analysis of a cylindrical composite of carbon...

EXPERIMENTAL DETERMINATION OF SPECTRAL INDICES BY SCANNING OF FUEL ROD IN THE IPEN/MB-01...

Mechanical-structural analysis of a stainless steel fuel rod under burst test co...

Numerical methodology for the elastic stress analysis in the design by analysis of...

Monte Carlo modelling of the patient and treatment delivery complexities for high...