Temperature and time effects of post-weld heat treatments on tensile properties and microstructure of Zircaloy-4

Echols, J. R.; Garrison, Lauren M.; Silva, Chinthaka M.; Lindquist, Elizabeth G.

doi:10.1016/j.jnucmat.2021.152952

Cited by 5 publications

(1 citation statement)

References 24 publications

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“…Zirconium alloy, particularly zirconium alloy-4 (Zr-4), was widely utilised as structural and cladding materials in pressurised water reactors, boiling water reactors and CANDU reactors. Because of its superior hydrothermal corrosion performance and appropriate mechanical qualities, it has a low thermal neutron absorption cross-section [5].…”

Section: Introductionmentioning

confidence: 99%

Strain rate susceptibility of stress corrosion cracking for commercial Zr702 used in spent nuclear fuel reprocessing

Liu

et al. 2023

Corrosion Engineering, Science and Technology

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Slow strain rate tensile (SSRT) experiments were applied to comprehensively examine the strain rate susceptibility of the stress corrosion cracking behaviour of commercial Zr702 used in the spent nuclear fuel reprocessing environment. Results revealed that layers formed on Zr702 in boiling HNO 3 solutions was composed of monoclinic ZrO 2 (m-ZrO 2 ) and tetragonal ZrO 2 (t-ZrO 2 ). With strain rates above 10 −4 s −1 , oxide layers ruptured rapidly, evidenced by the drop down of opened circuit potential (OCP). However, the OCP curve displayed fluctuation with 10 −5 s −1 during straining, indicating that oxide layer alternately ruptured and repaired, resulting in the thickening of the oxide layer and increasement of stress corrosion cracking susceptibility.

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Section: Introductionmentioning

confidence: 99%