Abstract
Production of Zirconium alloys for nuclear power reactor comprises of a number of steps during swaging and each step influences microstructural and mechanical properties of the finished product. The Zircaloy-4 was subjected to cold swaging to reduce its cross section gradually from 23 to 16 mm diameter via several passes of swaging followed by intermediate vacuum annealing at 732 °C for 3 h. EBSD was carried out to study the influence of twinning in the Zr-4 alloy. Twinning is observed in swaged ({11\(\bar{2}\)2}〈11\(\bar{2}\bar{3}\)〉) and annealed ({11\(\bar{2}\)1}〈11\(\bar{2}\bar{6}\)〉) samples. TEM was done to substantiate the role of dislocation density. It is observed that several swaging and annealing treatments have improved tensile strength and fracture toughness of the Zr-4 alloy.
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The authors would like to thank Board of Research in Nuclear Sciences (BRNS), Mumbai, India for sponsoring this work.
Funding
This research was funded by Board of Research in Nuclear Sciences (BRNS), Mumbai, India (Grant No. EDD/16/17/034/BRNS/RJAG.)
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Singh, G., Tiwari, A., Agarwal, V. et al. Tensile and Fracture Behaviour of Zr-4 Alloy Processed Through Swaging. Trans Indian Inst Met 73, 955–965 (2020). https://doi.org/10.1007/s12666-020-01874-3
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DOI: https://doi.org/10.1007/s12666-020-01874-3