Tensile and Fracture Behaviour of Zr-4 Alloy Processed Through Swaging

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 diame...

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Bibliographic Details
Published inTransactions of the Indian Institute of Metals Vol. 73; no. 4; pp. 955 - 965
Main Authors Singh, Gaurav, Tiwari, Abhishek, Agarwal, Vikas, Jayaganthan, R., Vishnu Narayanan, K. I., Arora, Umesh Kumar, Srivastava, Dinesh
Format Journal Article
LanguageEnglish
Published New Delhi Springer India 01.04.2020
Springer Nature B.V
Subjects
Chemistry and Materials Science
Cold working
Corrosion and Coatings
Dislocation density
Fracture toughness
Materials Science
Mechanical properties
Metallic Materials
Original Article
Swaging
Tensile strength
Tribology
Twinning
Vacuum annealing
Zircaloys (trademark)
Zirconium alloys
Zirconium base alloys
Annealing
Fracture
Zr-4
Swaging
EBSD
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Summary: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 2 ¯ 2}〈11 2 ¯ 3 ¯ 〉) and annealed ({11 2 ¯ 1}〈11 2 ¯ 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.
ISSN:0972-2815
0975-1645
DOI:10.1007/s12666-020-01874-3