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

Onimus, F.; Gélebart, Lionel; Brenner, Rénald

doi:10.1016/j.ijplas.2022.103272

Cited by 21 publications

(6 citation statements)

References 103 publications

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“…Using the model combined with FEM homogenization, it was possible to simulate strain localization, softening and associated ratcheting in irradiated zircalloy subjected to cyclic loading. Thermal creep, irradiation creep and irradiation induced growth were taken into account in the constitutive model reported in [44]. Two micro-macro transition schemes enabling to obtain the response of the polycrystal from single crystal consistutive model were compared, namely the self-consistent method and FFT solver AMITEX_FFTP.…”

Section: Of 17mentioning

confidence: 99%

Modelling Irradiation Effects in Metallic Materials using the Crystal Plasticity Theory

Frydrych¹

2023

Preprint

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The review starts by highlighting the significance of nuclear power plants in contemporary world, especially its indispensable role in the global efforts to reduce CO2 emissions. Then, it describes the impact of irradiation on microstructure and mechanical properties of reactor structural materials. The main part provides the reader with a thorough overview of crystal plasticity models developed to address the irradiation effects so far. All three groups of most important materials are included. Namely, the Zr alloys used for fuel cladding, austenitic stainless steels used for reactor internals and ferritic steels used for reactor pressure vessel. Other materials, especially those considered for construction of future fission and fusion nuclear power plants, are also mentioned. The review pays also special attention to ion implantation and instrumented nanoindentation which are a common way to substitute costly and time-consuming neutron irradiation campaigns.

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Section: Of 17mentioning

confidence: 99%

Modelling Irradiation Effects in Metallic Materials using the Crystal Plasticity Theory

Frydrych¹

2023

Preprint

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“…Thermal creep, irradiation creep, and irradiation-induced growth were taken into account in the constitutive model reported in [59]. Two micro-macro transition schemes enabling to obtain the response of the polycrystal from the single crystal consistutive model were compared, namely the self-consistent method and FFT solver AMITEX_FFTP.…”

Section: Materials For Fuel Claddingmentioning

confidence: 99%

Modelling Irradiation Effects in Metallic Materials Using the Crystal Plasticity Theory—A Review

Frydrych

2023

Crystals

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The review starts by highlighting the significance of nuclear power plants in the contemporary world, especially its indispensable role in the global efforts to reduce CO2 emissions. Then, it describes the impact of irradiation on the microstructure and mechanical properties of reactor structural materials. The main part provides the reader with a thorough overview of crystal plasticity models developed to address the irradiation effects so far. All three groups of the most important materials are included. Namely, the Zr alloys used for fuel cladding, austenitic stainless steels used for reactor internals, and ferritic steels used for reactor pressure vessels. Other materials, especially those considered for construction of future fission and fusion nuclear power plants, are also mentioned. The review also pays special attention to ion implantation and instrumented nanoindentation which are common ways to substitute costly and time-consuming neutron irradiation campaigns.

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“…Zirconium alloy has become the preferred material for positioning grids in nuclear reactors because of its good nuclear properties, low thermal neutron absorption crosssection, high tensile strength, good corrosion resistance and comprehensive mechanical properties [1][2][3][4][5][6]. A positioning grid is a key clamping structure for fixing the transverse and axial positions of fuel assemblies in nuclear reactors [7][8][9][10][11].…”

Section: Introductionmentioning

confidence: 99%

Study on Formability Improvement of Zr-4 Sheets Based on Texture Optimization

Liu,

Song,

Deng

et al. 2024

Metals

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A positioning grid is a key clamping structure for fixing the transverse and axial positions of fuel assemblies in nuclear reactors, and it is generally prepared by the transverse stamping of a Zr-4 sheet. However, the texture formed in the processing process of Zr-4 sheets can affect formability, resulting in cracking in the stamping process. Therefore, the relationship between the formability of Zr-4 sheets and the normal Kearns factor (Fn) of basal texture was studied in this paper. The results showed that the Zr-4 sheet with an Fn equaling 0.720, prepared by an isobaric reduction rolling process, would crack in the stamping process. To avoid the cracking during stamping, the formability improvement of Zr-4 sheets based on texture optimization was discussed. By using the finite element model (FEM) and a visco plastic self-consistent (VPSC) model coupled simulation, the relationship between the initial textures and formabilities of Zr-4 sheet is established. It is found that the hardening exponents (n) decreased with increasing Fns in VPSC simulations. Meanwhile, as the Fn increases, cracks are prone to occur at the bottom corner of the stamped sheet in finite element simulation. Given the results from FEM and VPSC simulations, it is proposed that the Fn should be controlled to be less than 0.7 for preventing cracks in the sheet during stamping. Additionally, a new rolling process named non-isobaric reduction rolling was designed in which the Fn of the Zr-4 sheet is successfully reduced to 0.690. The stamping results indicate that the sheet is free of cracks under an Fn of 0.690. Therefore, texture optimization with the proposed rolling process can improve the formability of Zr-4 sheets, which effectively solves the cracking problem of Zr-4 sheets.

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

Cited by 21 publications

References 103 publications

Modelling Irradiation Effects in Metallic Materials using the Crystal Plasticity Theory

Modelling Irradiation Effects in Metallic Materials using the Crystal Plasticity Theory

Modelling Irradiation Effects in Metallic Materials Using the Crystal Plasticity Theory—A Review

Study on Formability Improvement of Zr-4 Sheets Based on Texture Optimization

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