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In situ irradiations of 15Cr/15NiTi and 15Cr/25NiTi model austenitic steels were performed at the Intermediate Voltage Electron Microscope (IVEM)-Tandem user Facility (Argonne National Laboratory) at 600 °C using 1 MeV Kr++. The experiment was designed in the framework of cladding development for the GEN IV Sodium Fast Reactors (SFR). It is an extension of previous high dose irradiations on those...
In Pressurized Water Reactors, zirconium hydrides precipitate in the matrix and could increase the oxidation rate of the claddings. To understand their effect, corrosion tests, TEM and μ-XRD analyses have been performed. This work showed that the oxidation rate and the oxygen diffusion coefficient in the oxide formed on massive hydride are much greater than those of Zircaloy-4. Moreover, oxide characterizations...
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