Abstract
The present study aims to explore ‘melting’ as a method for environment friendly management of radioactive metallic waste, viz. clad (Zirconium alloy), structural materials (stainless steel, etc.), with a view to reduce the volume of the radioactive metallic waste and develop a waste form with acceptable product durability parameters. Zircaloy–Stainless steel alloy (in w/w 85:15), in the form of monolithic waste form, was prepared in kilogram scale using vacuum induction melting furnace and the base alloy was pourable in between 1200 and 1300 °C depending on the starting material compositions and soaking time given. The microstructure of the as-cast alloy shows variations in structure spatially, but overall the matrix is dominated by Zr3Fe with α-Zr, Zr2(Fe,Cr), Zr(Fe,Cr), Zr(Fe,Cr)2 randomly distributed. Volume reduction factor (charge-to-product volume ratio) was found to be close to 10 in the present case.
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Acknowledgements
Authors are grateful to the Editors of this issue to kindly consider this paper. The study was sponsored by Bhabha Atomic Research Centre, Department of Atomic Energy, Government of India.
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Department of Atomic Energy, Government of India, Development of New Alloys (XII-N-R&D-19), Pranesh Sengupta.
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Sengupta, P., Kumar, R., Gupta, S. et al. Microstructural and Micro-Analysis of Zirconium: Stainless Steel alloys for Radioactive Metallic Waste Management. Trans Indian Inst Met 75, 1043–1050 (2022). https://doi.org/10.1007/s12666-022-02553-1
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DOI: https://doi.org/10.1007/s12666-022-02553-1