Abstract
Coating of zirconium alloys is a promising approach for improving various properties of the cladding of fuel elements, including physical, mechanical properties, corrosion resistance and reduction of radiation damage. In this paper, SiC coatings with thicknesses of 100, 200, and 300 microns were deposited by selective laser sintering (SLS) on Zr-1Nb alloy substrates at a laser power of 150 W. The 200 μm layer deposition registered the least contact depth during macro-scratch test to a maximum depth of about 25 μm into the coating. The uniformity and less porosity of the coatings is observed on the transverse sections in the entire variant. Analysis of the phase composition of the coating revealed the formation of silicon carbide phases (6H & 4H), with protective oxides of Al2O3, Y2O3, SiO2 and YAlO3. High coating adhesion was noticed with results of the scratch tests showing no delamination regardless of the higher loads used. However, partial chippings and transverse cracks were observed. The results obtained indicate the need for further research to improve the porosity of the surface structure of the coating and to conduct other necessary tests.
Highlights
Since 2011 following the tragic Fukushima Daiichi Nuclear Power Plant accident, the quest for Accident Tolerant Fuel (ATF) has become extremely essential towards shaping the safety path of future nuclear industries
Nano to micro scratch tests were incompatible to the coating due to the higher level of adhesiveness exhibited by the coatings, macro-scratch test was carried out involving constant loads of 50 N to 100 N
EDS taken along the scratch path shows the presence of some remains of the coating material composition such as Si, O, Al, and substrate material Zr being the majority
Summary
Since 2011 following the tragic Fukushima Daiichi Nuclear Power Plant accident, the quest for Accident Tolerant Fuel (ATF) has become extremely essential towards shaping the safety path of future nuclear industries. Though zirconium-based alloys have gained acceptance over decades in the nuclear industry, the submissiveness of zirconium during Loss of Coolant Accident (LOCA) event in which the oxidation response of zirconium at a higher temperature speedily deteriorates in its integrity under such condition calls for the need in enhancing the generation of cladding materials [1]. One of the approaches in enhancing the fuel cladding tube includes protective coatings on zirconium based alloys. Thin coatings are anticipated to have marginal importance in terms of the thermomechanical properties of zirconium based claddings [2]. These coatings do not exceptionally change the central physics in LWRs [3] but are likely to improve the heat transfer performance of the cladding [4]. Some studies have proven various depositions on zirconium based alloy substrates effective in overcoming oxidation, resisting corrosion and minimizing the vulnerability of grid-to-rod fretting failures
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