Polycrystalline modeling of the behavior of neutron-irradiated recrystallized zirconium alloys during strain path change tests

Onimus, F.; Bono, M.; Verhaeghe, Bénédicte; Soniak, A.; Pilvin, P.

doi:10.1016/j.ijplas.2020.102835

Cited by 11 publications

(6 citation statements)

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“…Simulations were performed in the isothermalisobaric ensemble with periodic boundary conditions along the three axes under 300 K and zero-applied pressure. The lattice parameters were deduced as the average of the box lengths, respectively along the x-axis (divided by 50), and the ẑ-axis (divided by 29), over 1 ns. The results of the simulations are given in table 1.…”

Section: Data Availability Statementmentioning

confidence: 99%

“…The change of mechanical properties after irradiation is essentially the result of the interactions between gliding dislocations and these numerous loops, which act as obstacles against dislocation glide. Transmission electron microscopy (TEM) observations conducted after mechanical testing on neutron irradiated zirconium alloy samples have furthermore revealed that moving dislocations are able to wipe loops close to their glide planes under sufficient applied stress creating cleared bands, or channels, free of loops [18][19][20][21][22][23][24][25][26][27][28][29].…”

Section: Introductionmentioning

confidence: 99%

See 1 more Smart Citation

Atomistically informed dislocation dynamics simulations: application to dislocation-loop interactions in zirconium

Dupuy,

Kassem,

Clouet

et al. 2024

Modelling Simul. Mater. Sci. Eng.

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Neutron irradiation of zirconium alloys leads to the formation of highdensities of small dislocation loops. Their interactions with gliding dislocations areresponsible for hardening and early necking of the material. Multi-scale numericalsimulations of the interactions between dislocations and loops are undertaken to predictthe mechanical properties evolution of these materials due to irradiation. Moleculardynamics simulations are first performed to assess the critical ingredients needed fordislocation dynamics simulations. Appropriate models and associated coefficients arethen introduced in dislocation dynamics simulations in order to reliably reproducethe dislocation line energy, the cross-slip process from basal to prismatic planes andthe mobility of straight and jogged dislocations. Based on this parametrization,interactions between dislocation and loops are finally computed with the two numericalmethods. Careful comparisons between the two types of simulation show qualitativeand quantitative agreement, opening the path to investigations of irradiation effects atthe grain scale through large scale dislocation dynamics simulations.

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Section: Data Availability Statementmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Atomistically informed dislocation dynamics simulations: application to dislocation-loop interactions in zirconium

Dupuy,

Kassem,

Clouet

et al. 2024

Modelling Simul. Mater. Sci. Eng.

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“…Furthermore, stress free samples have also been irradiated in the same conditions to measure the irradiation induced growth strain. To obtain the target hoop stress, the tubes were pressurized with an internal pressure ( ) such that at irradiation temperature, the hoop stress is given by the following approximated formula 28 Eq. 1.…”

Section: Materials and Mechanical Test Data Basementioning

confidence: 99%

Polycrystalline Simulations of In-Reactor Deformation of Zircaloy-4 Cladding Tubes during Nominal Operating Conditions

Gicquel,

Onimus,

Brenner

et al. 2023

Zirconium in the Nuclear Industry: 20th International Symposium

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Fuel cladding tubes made of zirconium alloys, are subjected in reactor to a complex loading history under nominal operating conditions. Furthermore, they exhibit a complex deformation behavior resulting from irradiation-induced growth, irradiation creep and thermal creep. For design and safety requirements, empirical models are usually used. To have robust physically based mechanical simulations, a self-consistent polycrystalline model has been developed. This model takes into account the various phenomena occurring at the grain scale, such as irradiation-induced growth and irradiation creep. Moreover, this model takes into account the crystallographic texture of the material and the mechanical interactions between grains, depending on their orientation. Furthermore, this model is able to handle complex mechanical loading. This model is first shown to reproduce well an experimental database of in-reactor deformation of zirconium alloys. Thanks to the polycrystalline nature of this model, the effect of grain shape and creep mechanisms at the grain scale on the simulated data have been studied in detail. Next, this polycrystalline model has been introduced into a 1D finite element method code, allowing the computation of stress and strain gradients through a thin cladding tube during a complex mechanical loading. This approach opens the way to physically based mechanical calculations at the component scale.

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“…From the difference between the current diameter and the initial diameter, the creep strain was computed. It should be pointed out that applying an internal pressure induces a biaxial stress state, with the axial stress equal to approximately half of the hoop stress (Onimus et al, 2020a).…”

Section: Mechanical Tests Data Basementioning

confidence: 99%

“…Another very different, and pragmatic, approach has also been proposed for the homogenization of the behavior of polycrystals (Cailletaud, 1992;Cailletaud and Pilvin, 1994). This method has been applied to zirconium alloys after irradiation (Onimus et al, 2020a;Onimus and Béchade, 2009) but has not been applied to in-reactor deformation of zirconium alloys in the open literature.…”

Section: -Introductionmentioning

confidence: 99%

Polycrystalline simulations of in-reactor deformation of recrystallized Zircaloy-4 tubes: Fast Fourier Transform computations and mean-field self-consistent model

Onimus

Gélebart

Brenner

2022

International Journal of Plasticity

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Polycrystalline modeling of the behavior of neutron-irradiated recrystallized zirconium alloys during strain path change tests

Cited by 11 publications

References 50 publications

Atomistically informed dislocation dynamics simulations: application to dislocation-loop interactions in zirconium

Atomistically informed dislocation dynamics simulations: application to dislocation-loop interactions in zirconium

Polycrystalline Simulations of In-Reactor Deformation of Zircaloy-4 Cladding Tubes during Nominal Operating Conditions

Polycrystalline simulations of in-reactor deformation of recrystallized Zircaloy-4 tubes: Fast Fourier Transform computations and mean-field self-consistent model

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