Influence of dynamic strain aging on the dislocation structure developed in Zircaloy-4 during low-cycle fatigue

Alvarez‐Armas, I.; Hereñú, S.

doi:10.1016/j.jnucmat.2004.07.002

Cited by 14 publications

(3 citation statements)

References 19 publications

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“…It depends on deformation rate and temperature, which govern the velocities of mobile dislocations and diffusing solute atoms, respectively. The DSA regime for Zircaloys has been reported to be 300-500°C for both monotonic and cyclic loading [Derep et al 1980, Ahn and Nam 1990, Moscato et al 1997, Alvarez-Armas and Herenu 2004. The DSA regime for Zr-2.5Nb under monotonic tensile loading was found to be in the temperature range of 250-350°C [Singh et al 2005].…”

Section: Cyclic Stress Response and Cyclic Stress-strain Behaviormentioning

confidence: 94%

“…Secondary cyclic hardening has been observed in several Zr-based alloys including Zr-Sn-Nb alloy [Tan et al 2006] and Zircaloys [Armas et al 1992, Moscato et al 1997, Armas et al 1996. The occurrence of secondary cyclic hardening in zirconium alloys was suggested to be associated with the development of secondary dislocations due to the activation of the dynamic strain aging [Alvarez- Armas and Herenu 2004].…”

Section: Cyclic Stress Response and Cyclic Stress-strain Behaviormentioning

confidence: 99%

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Fatigue Behavior of Pressure Tube Material Zr-2.5Nb in Air and in Simulated CANDU-Reactor Water Environments

Li¹,

Soppet²,

Natesan³

2014

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An experimental program was initiated to develop fatigue data in strain-controlled conditions for an assessment of the fatigue behavior of Zr-2.5Nb pressure tube material in support of CANDU reactors for Atomic Energy of Canada Limited (AECL)/Chalk River Laboratories (CRL). Fatigue tests were conducted on specimens fabricated from a Zr-2.5Nb pressure tube to determine the fatigue performance in air and in simulated CANDUreactor water environments. This report summarizes the fatigue data of Zr-2.5Nb material obtained in both environments. Fatigue tests in air were performed under constant total strain amplitudes in the fully reversed (R=-1) strain control. Fatigue behavior of Zr-2.5Nb pressure tube material was examined over a range of total strain amplitudes from 0.4 to 0.75% at 300°C with a balanced triangular wave form (equal strain rates in tension and in compression) at a strain rate of 0.4%/s. The temperature dependence of the fatigue response was examined at 20 and 100°C at total strain amplitude of 0.6%. The strain rate dependence of the fatigue performance was investigated by applying an unbalanced triangular waveform with a slower strain rate of 0.004%/s in tension and a faster strain rate of 0.4%/s in compression. Fatigue tests in water environments were performed under the stroke control mode. The axial stroke response was correlated with the axial strain control from the air tests, and was used to provide control for the fatigue tests in the autoclave system. Fatigue behavior of Zr-2.5Nb pressure tube material was examined over a range of total strain amplitudes from 0.45 to 0.75% at 300°C with an unbalanced triangular waveform with a slower strain rate of 0.004%/s in tension and a faster strain rate of 0.4%/s in compression in lowdissolved oxygen (DO) LiOH-containing water. Fatigue data were analyzed to obtain the strain-life relation, the cyclic stress response during fatigue cycling, half-life hysteresis loops, and half-life cyclic stress-strain curves. The cross-sectional fracture surfaces and longitudinal surfaces of the gage section of tested specimens were examined by scanning electron microscopy (SEM) to understand the fatigue crack initiation and propagation behavior in this material. The fatigue life of Zr-2.5Nb was significantly reduced in simulated CANDU-reactor water environments at 300°C, compared to the fatigue data obtained in air. The synergistic effect of the aqueous environment and the strain rate is most detrimental to the fatigue resistance of Zr-2.5Nb. The fatigue life of Zr-2.5Nb in water under the slow-fast cyclic loading was reduced in both high-strain and low-strain amplitudes when compared with the fatigue data in air under the fast-fast cycling. The influence of the aqueous environment on the fatigue resistance is more pronounced in the high strain amplitudes than in the low strain amplitudes when compared with the fatigue data in air under slow-fast cyclic loading. Significant reduction in fatigue life was observed at 300°C in air when a lower strain rate (0.004%/s) was ap...

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Section: Cyclic Stress Response and Cyclic Stress-strain Behaviormentioning

confidence: 94%

Section: Cyclic Stress Response and Cyclic Stress-strain Behaviormentioning

confidence: 99%

Fatigue Behavior of Pressure Tube Material Zr-2.5Nb in Air and in Simulated CANDU-Reactor Water Environments

Li¹,

Soppet²,

Natesan³

2014

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“…Low cycle fatigue (LCF) of Zr-4 was studied very deeply in recent two decades [2][3][4][5]. The results of tests on Zr-4 in recrystallized and stress-relieved conditions at RT and 400℃ show that heat treatment conditions have great influences on LCF properties of Zr-4.…”

Section: Introductionmentioning

confidence: 99%

Bending Ratcheting Behavior of Zircaloy-4 Alloy at Room Temperature

Guo

Sun

et al. 2013

AMR

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In this paper, a series of bending cyclic tests under stress controlled were conducted at room temperature on Zircaloy-4 (Zr-4) to investigate its bending ratcheting behavior. The effects of mean stress and stress amplitude on the bending ratcheting behavior were experimentally studied, respectively. The experimental results show that the ratcheting strain of the material is very sensitive to mean stress and stress amplitude. It can be concluded that ratcheting strain level increases with increasing mean stress and stress amplitude.

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The Simulation and Experiment of In 718 in Warm Laser Shock Processing Without Coating

et al. 2021

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Influence of dynamic strain aging on the dislocation structure developed in Zircaloy-4 during low-cycle fatigue

Cited by 14 publications

References 19 publications

Fatigue Behavior of Pressure Tube Material Zr-2.5Nb in Air and in Simulated CANDU-Reactor Water Environments

Fatigue Behavior of Pressure Tube Material Zr-2.5Nb in Air and in Simulated CANDU-Reactor Water Environments

Bending Ratcheting Behavior of Zircaloy-4 Alloy at Room Temperature

The Simulation and Experiment of In 718 in Warm Laser Shock Processing Without Coating

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