Influence of Water Radiolysis on the Passive Properties of 316L-Stainless Steel.

This work aims to study the effect of radiolytic species induced by water radiolysis on the passive behavior of 316L stainless steel. For this purpose, the stainless steel/neutral and aerated 0.02 M NaSO, electrolyte solution interface was irradiated with proton beams.

Cs diffusion mechanisms in UO investigated by SIMS, TEM, and atomistic simulations.

Experimental investigations and atomistic simulations are combined to study the cesium diffusion processes at high temperature in UO. After Cs implantation in UO samples, diffusion coefficients are determined using the depth profile evolution after annealing as measured by secondary ion mass spectrometry. An activation energy of 1.

Effect of the Oxygen Potential on the Mo Migration and Speciation in UO and UO.

Molybdenum is an abundant element produced by fission in the nuclear fuel UO in a pressurized water reactor. Although its radiotoxicity is low, this element has a key role on the fuel oxidation and other fission products migration, in particular in the case of an accidental scenario. This study aims to characterize the behavior of molybdenum in uranium dioxide as a function of environmental conditions (oxygen partial pressure, high temperature, UO oxidation) typical of an accidental scenario.

Chemical growth and photochromism of silver nanoparticles into a mesoporous titania template.

Elaboration of mesoporous titanium oxide film supporting silver nanoparticles is described. Mesoporous titanium oxide films are characterized by TEM analysis. Titania films are infiltrated with a silver salt solution and chemical reduction treatments are performed using either a NaBH(4) or a formaldehyde solution.