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A Study on Zirconium Rich Uranium–Zirconium Alloys

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Abstract

Uranium–zirconium alloy is the potential candidate materials as metallic fuels for nuclear reactor applications. Along with other properties, volumetric stability is an important issue for these types of fuels. In this work investigations were carried out on the zirconium rich uranium–zirconium alloys (i.e. U–50 wt% Zr, U–60 wt% Zr and U–70 wt% Zr) in as-cast as well as in heat treated conditions. Microstructural and dilatometric studies were carried out along with X-ray diffraction analysis to evaluate the phase content as well as the phase transformation behaviour of these alloys under different heat treated conditions.

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Acknowledgments

The authors are grateful to Dr. T. R. G. Kutty, Head, FPES, RMD and his group for SEM and dilatometric analysis. Dr. C. B. Basak has provided colossal support on work planning. Shri S. Das, Uranium Extraction Division has allowed using his equipments for sample melting and cutting. And, last, but not the least, thanks to the members of ED&AS, AFD for their help on sample preparation.

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Authors and Affiliations

  1. Nuclear Fuels Group, Bhabha Atomic Research Centre, Trombay, Mumbai, 400085, India

    Ambar Chandra Bagchi, Garimella Jagannath Prasad, Kirity Bhusan Khan & Rishi Pal Singh

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  1. Ambar Chandra Bagchi
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  2. Garimella Jagannath Prasad
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  3. Kirity Bhusan Khan
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  4. Rishi Pal Singh
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Correspondence to Ambar Chandra Bagchi.

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Bagchi, A.C., Prasad, G.J., Khan, K.B. et al. A Study on Zirconium Rich Uranium–Zirconium Alloys. Trans Indian Inst Met 67, 123–130 (2014). https://doi.org/10.1007/s12666-013-0326-y

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  • DOI: https://doi.org/10.1007/s12666-013-0326-y

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