The project is accompanied by numerical studies of heat transfer of supercritical water in fuel assemblies and by material tests of candidate cladding alloys, performed by the consortium and supported by additional tests of the Joint Research Centre of the European Commission.
However, corrosion resistance of the laser cladded alloy was reduced by almost an order of magnitude compared to that of the as-cast alloy mainly due to the presence of cracks and pores in the cladded layer.
The new geometry performance is evaluated using a commercial 304 L stainless steel, an aluminum alloy including advanced 3D-printed material, a high nickel 718-alloy, tungsten, and an advanced fuel cladding FeCrAl alloy.
Advanced cladding alloys (Duplex DX/D4, M5®, ZIRLO™) will be applied in further tests.
Advanced cladding materials with potentially enhanced accident tolerance will yield different light-water reactor performance and safety characteristics than the present zirconium-based cladding alloys.
In this paper, the combination of first-principles materials modeling and high-resolution electron microscopy is used to identify the structure of this sub-oxide phase, bringing us a step closer to developing strategies to mitigate aqueous oxidation in Zr alloys and prolong the operational lifetime of commercial fuel cladding alloys.
Low neutron absorption, high heat conductivity, good corrosion resistance in water, low chemical interaction with cladding (zirconium alloy) and UO2 in normal and accident conditions, technological ability — are the requirements of the matrix material [1].
The results show that the LDPSC can be divided to three zones: cladding zone, alloying zone and heat affected zone.
In the present study, an attempt was made to improve the wear resistance and the corrosion resistance of AZ91HP magnesium alloy by laser cladding Al Si eutectic alloy.
However, these results relate not only to the Co content in the laser-clad alloys, but also the number of overlapping tracks.
