Texture Analysis and Fracture Behavior of Zircaloy-4 Processed Through Swaging

Singh, Gaurav; Jayaganthan, R.; Arora, Umesh Kumar; Narayanan, K. I. Vishnu; Srivastava, D.

doi:10.1007/s13632-020-00634-5

Cited by 7 publications

(3 citation statements)

References 22 publications

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“…These results are for swaged samples at different feed rates and it suggests that increasing the feed rate increases the compressive residual stresses on the surface while tensile stresses are nearly similar on increasing the feed rates. With these results, we suggest that 1.25 m/min feed rate is good for producing swaged Z-4 alloy, because of the good combination of mechanical properties of tensile strength (535.50 MPa), ductility (19.84%) and fracture toughness (44.37 MPa•m 0.5 ) reported in our earlier work [24]. Further annealing treatment will decrease the tensile residual stress at the center of Zr-4 alloy rod.…”

Section: Deep Hole Drillingsupporting

confidence: 64%

“…Zirconium alloy is used in nuclear fission reactor applications due to its superior mechanical properties compared to other structural material like stainless steel [22]. Zirconium alloys have a good combination of strength and ductility, high corrosion and oxidation resistance and a low neutron absorption cross section area [23][24][25][26]. Residual stresses are induced into the materials due to plastic deformation, annealing, phase transformation and welding in material components [27].…”

Section: Introductionmentioning

confidence: 99%

“…Samples are polished by emery papers because surface defects may affect the strain relaxation readings. Young's modulus and Poisson's ratio of Zr-4 alloy are 99 GPa and 0.37, respectively [23,24]. The tensile properties (yield strength and tensile strength) of Zr-4 alloys are taken from our earlier work [23].…”

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confidence: 99%

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Finite Element Analysis and Experimental Evaluation of Residual Stress of Zr-4 alloys Processed through Swaging

Singh

Kalita

Narayanan³

et al. 2020

Metals

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Zirconium alloy has been extensively used as a cladding material in nuclear power reactors due to its low neutron absorption cross section, excellent mechanical properties, and corrosion resistance. The influence of the swaging parameter, feed rate (0.7, 1.25, 2 m/min) on residual stress induced in Zr-4 alloy is investigated in the present work. A three-dimensional finite element model was implemented in the Deform 3D software to simulate the rotary swaging (RS) process over a circular rod of Zr-4 alloy. The simulation results based on the 3D framework provide a detailed insight of residual stress, true stress versus true strain and force applied over the rod during the multiple pass swaging process; the results are compared with experimental results. The experimental hole drilling method is used to determine the residual stresses on swaged zirconium alloy at different feed rates (0.7, 1.25, and 2 m/min). A similar trend of residual stress between experimental and numerical results from the surface to the center on the swaged rod samples is observed. The same magnitude of residual stress at the surface of the swaged Zr-4 rod is also observed. It is found to be compressive at the surface and tensile in the center of the samples, as observed in the present work.

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Section: Deep Hole Drillingsupporting

confidence: 64%