Uranium melting study on Yttria coated HDG with SiC interlayer for pyrochemical reprocessing application
Madhura, B.; Jagadeeswara Rao, Ch.; Vetrivendan, E.; Ningshen, S.; Venkatesh, P.
Proceedings of the research scholars meet on materials science and engineering of nuclear materials: programme and abstracts2018
Proceedings of the research scholars meet on materials science and engineering of nuclear materials: programme and abstracts2018
AbstractAbstract
[en] Yttria (Y2O3) coated High density Graphite (HDG) crucibles are extensively used as the process crucibles in pyrochemical reprocessing application. The durability of HDG crucible can be further enhanced with carbide interlayers by avoiding interaction between yttria and graphite beyond 1400 °C. Thus, the present study focus on examine the durability and performance of yttria coated HDG with and without Silicon Carbide interlayer during uranium melting cycles. Novel pack cementation method was used to develop SiC interlayer followed by top yttria coating by Atmospheric Plasma Spray (APS) method. The performance of coating improved by introducing SiC interlayer and the same was analyzed by XRD, SEM, and thermal cycle studies. The results demonstrated that yttria coated HDG crucibles with SiC interlayer withstood 5 uranium melting cycles without any cracking or delamination of coating. (author)
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Source
Indira Gandhi Centre for Atomic Research, Kalpakkam (India); [98 p.]; 2018; [1 p.]; RSM-MSENM: research scholars meet on materials science and engineering of nuclear materials; Kalpakkam (India); 7-9 May 2018; Article ID: O-27
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Book
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Conference
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Descriptors (DEI)
Descriptors (DEC)
CARBON, CHALCOGENIDES, CHEMICAL REACTIONS, COHERENT SCATTERING, CRACKING, DECOMPOSITION, DEPOSITION, DIFFRACTION, ELEMENTS, MINERALS, NONMETALS, OXIDES, OXYGEN COMPOUNDS, PYROLYSIS, REPROCESSING, SCATTERING, SEPARATION PROCESSES, SURFACE COATING, TEMPERATURE RANGE, TESTING, THERMOCHEMICAL PROCESSES, TRANSITION ELEMENT COMPOUNDS, YTTRIUM COMPOUNDS
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