Technologie Nucléaire - Réacteurs
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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...
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...
Project and construction of energy degrading and scattering plates for electron beam...
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