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Main Authors: Aguzzi, Fabrizio E., Rabazzi, Santiago M., Armoa, Martín S., Pairetti, César I., Albanesi, Alejandro E.
Format: Preprint
Published: 2025
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Online Access:https://arxiv.org/abs/2506.02807
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author Aguzzi, Fabrizio E.
Rabazzi, Santiago M.
Armoa, Martín S.
Pairetti, César I.
Albanesi, Alejandro E.
author_facet Aguzzi, Fabrizio E.
Rabazzi, Santiago M.
Armoa, Martín S.
Pairetti, César I.
Albanesi, Alejandro E.
contents This work presents an open-source interface that couples the viscoplastic self-consistent (VPSC) model capable of simulating anisotropic creep and irradiation growth in polycrystalline materials with the finite element solver Code_Aster. The interface enables the simulation of the micromechanical response of irradiated zirconium alloy components by integrating grain-level constitutive behavior into a structural FEM framework. A key feature is the automated rotation of stress and strain tensors between the global FEM frame and the local crystallographic axes, a transformation not natively supported by Code_Aster. The elastic strain is recovered analytically using the inverse of the self-consistently stiffness tensor provided by VPSC. As a demonstration, the framework is applied to an actual model of a pressurized water reactor (PWR) spacer grid, based on a patented design, capturing nonlinear contact and the anisotropic response of the cladding and grid. Simulations reveal the micromechanisms controlling the evolution of clearance between components and highlight the role of crystallographic texture in mitigating wear. In particular, a texture with a high fraction of prismatic planes oriented in the normal direction of the grid appears to be the most suitable for spacer design, as it minimizes clearance and contributes to wear resistance. The interface offers a flexible, extensible platform for high-fidelity simulations in nuclear fuel performance analysis.
format Preprint
id arxiv_https___arxiv_org_abs_2506_02807
institution arXiv
publishDate 2025
record_format arxiv
spellingShingle An open-source finite element toolbox for anisotropic creep and irradiation growth: Application to tube and spacer grid assembly
Aguzzi, Fabrizio E.
Rabazzi, Santiago M.
Armoa, Martín S.
Pairetti, César I.
Albanesi, Alejandro E.
Computational Physics
This work presents an open-source interface that couples the viscoplastic self-consistent (VPSC) model capable of simulating anisotropic creep and irradiation growth in polycrystalline materials with the finite element solver Code_Aster. The interface enables the simulation of the micromechanical response of irradiated zirconium alloy components by integrating grain-level constitutive behavior into a structural FEM framework. A key feature is the automated rotation of stress and strain tensors between the global FEM frame and the local crystallographic axes, a transformation not natively supported by Code_Aster. The elastic strain is recovered analytically using the inverse of the self-consistently stiffness tensor provided by VPSC. As a demonstration, the framework is applied to an actual model of a pressurized water reactor (PWR) spacer grid, based on a patented design, capturing nonlinear contact and the anisotropic response of the cladding and grid. Simulations reveal the micromechanisms controlling the evolution of clearance between components and highlight the role of crystallographic texture in mitigating wear. In particular, a texture with a high fraction of prismatic planes oriented in the normal direction of the grid appears to be the most suitable for spacer design, as it minimizes clearance and contributes to wear resistance. The interface offers a flexible, extensible platform for high-fidelity simulations in nuclear fuel performance analysis.
title An open-source finite element toolbox for anisotropic creep and irradiation growth: Application to tube and spacer grid assembly
topic Computational Physics
url https://arxiv.org/abs/2506.02807