Mechanisms for decoration of dislocations by small dislocation loops under cascade damage conditions

Trinkaus, H.; Singh, B.N.; Foreman, A.J.E.

doi:10.1016/s0022-3115(97)00230-4

Cited by 115 publications

(38 citation statements)

References 25 publications

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“…1-D gliding clusters reduce the number of dislocation loops (so-called matrix damage) for they are primary absorbed on grain boundaries and dislocations. These clusters also decorate pre-existing dislocations thus immobilizing them and, according to the cascade induced source hardening (CISH) model [32,34] increasing the yield stress in irradiated materials. Also, ½<111> glissile loops interacting with each-other create <100> loops by the mechanism described recently [35].…”

Section: Discussionmentioning

confidence: 99%

“…Fourth, according to [35] reactions between ½<111> clusters/loops leading to the formation of <100> clusters occur in a rather narrow size range, NSIA~30-50. Therefore immobilization of these clusters reduces the probability of <100> cluster/loop formation Fifth, slowing down or immobilizing the glissile clusters should reduce or even prevent dislocation decoration and thus reducing the CISH contribution [32,34] which is a positive factor in view of the plastic instability observed in irradiated materials beyond a certain dose.…”

Section: Discussionmentioning

confidence: 99%

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The role of nickel in radiation damage of ferritic alloys

et al. 2015

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According to the modern theory damage evolution under neutron irradiation depends on the fraction of self-interstitial atoms (SIAs) produced in the form of one-dimensionally glissile clusters. These clusters, having a low interaction cross-section with other defects, are absorbed mainly by grain boundaries and dislocations creating the so-called production bias. It is known empirically that addition of certain alloying elements influence many radiation effects, including swelling, however the mechanisms are unknown in many cases. In this paper we report the results of an extensive multi-technique atomistic level modeling study of SIA clusters mobility in bcc Fe-Ni alloys. We have found that Ni interacts strongly with the periphery of clusters affecting their mobility. The total effect is defined by the number of Ni atoms interacting with the cluster at the same time and can be significant even in low-Ni alloys. Thus 1nm (37SIAs) cluster is practically immobile at T<500K in the Fe-0.8at.% Ni alloy. Increasing cluster size and Ni content enhance cluster immobilization. This effect should have quite broad consequences in void swelling, matrix damage accumulation and radiation induced hardening and the results obtained help to better understand and predict the effects of radiation in Fe-Ni ferritic alloys.

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Section: Discussionmentioning

confidence: 99%

Section: Discussionmentioning

confidence: 99%

The role of nickel in radiation damage of ferritic alloys

et al. 2015

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“…Molecular dynamics (MD) simulations studies using many-body potentials of the embedded atom method (EAM) type have proven to be very successful in the description of the first stage of damage production [2,3]. The modeling of the second stage has historically been undertaken by rate theory [4][5][6]. However, the application of kinetic Monte Carlo (kMC) simulations to diffusion processes [7,8] is starting to gain acceptance among the radiation damage community.…”

Section: Introductionmentioning

confidence: 99%

Simulation of damage evolution and accumulation in vanadium

Alonso¹,

Caturla²,

Rubia³

et al. 1999

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“…These clusters are created within the displacement cascade and glide to the dislocation where they are trapped. [23][24][25][26][27][28] Thus, the increase in the yield strength and the appearance of the yield point drop at high defect densities (high irradiation doses) is attributed to segments of the pre-existing dislocations breaking free from the atmosphere to create a dislocation source. [27,28] The source then generates the dislocations of the same type needed to create the channel.…”

Section: Case1 Dislocation Interactions With Frank Loopsmentioning

confidence: 99%

Dislocation–obstacle interactions: Dynamic experiments to continuum modeling

Robertson

Beaudoin

Al‐Fadhalah

et al. 2005

Materials Science and Engineering: A

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Incorporating the interaction of dislocations with obstacles remains a challenge in the development of predictive large-scale plasticity models. The need is particularly important in the elastic-plastic transition region where these interactions can dominate the behavior. By combining post-mortem analysis with dynamic straining in the transmission electron microscope, the atomic processes governing glissile dislocation reactions and interactions with obstacles has been determined. This information has been incorporated at least phenomenologically in models to assess the macroscopic stress-strain response. Two examples will be presented to demonstrate the methodology. The first example considers the interaction of dislocations with small vacancy Frank loops and the formation of defect-free channels in copper, and the second with the influence of imperfect annealing twin boundaries on the macroscopic stress-strain response in silver. In both examples, the importance of grain and twin boundaries as dislocation sources will be demonstrated.

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Mechanisms for decoration of dislocations by small dislocation loops under cascade damage conditions

Cited by 115 publications

References 25 publications

The role of nickel in radiation damage of ferritic alloys

The role of nickel in radiation damage of ferritic alloys

Simulation of damage evolution and accumulation in vanadium

Dislocation–obstacle interactions: Dynamic experiments to continuum modeling

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