{"title":"Crystal plasticity model for UO2: Introduction of the dislocation climbing and coupling with the thermally activated gliding","authors":"S. ElBez , M. Garajeu , B. Michel","doi":"10.1016/j.jnucmat.2025.156083","DOIUrl":null,"url":null,"abstract":"<div><div>Modelling of viscoplastic behaviour of <span><math><mrow><mi>U</mi><msub><mi>O</mi><mn>2</mn></msub></mrow></math></span> nuclear fuel at high temperature is of major interest to analyze the risk of cladding failure in power transient condition where pellet to cladding mechanical interaction occurs. In this study, we investigate the impact of dislocation climbing on the viscoplastic behaviour of <span><math><mrow><mi>U</mi><msub><mi>O</mi><mn>2</mn></msub></mrow></math></span> single crystal at high temperature where climbing mechanism is activated by vacancy diffusion. The modelling framework is that of an existing crystal plasticity law devoted to thermally activated gliding for lower temperatures. The constitutive equation of the crystal plasticity model are modified in order to add dislocation interaction hardening and stored dislocation recovery. The latter is assessed with dynamic recovery induced by cross slip and static recovery induced by dislocation climbing. A phenomenological model is proposed to compute the dislocation climbing velocity and the associated dislocation density recovery rate. The dislocation gliding velocity law is also improved with a physically based formulation introducing the activation energy for a double kink mechanism. The complete model, for low and high temperatures, is built with a harmonic coupling function enabling a more physically based formulation of the constitutive equations devoted to each mechanism. An implicit numerical implementation of the resulting model is proposed with a finite strain formulation in the framework of the MFront open source tool. A first validation of the complete model has been done with experiment/simulation comparisons for single crystal creep compression tests. In this first step, the validation is limited to orientations where only the modes 1 and 2 (soft and hard slip modes) are suspected of having a major contribution to the viscoplastic behaviour. Thanks to the contribution of dislocation gliding, interaction and climbing we can explain the evolution of the compression flow stress as a function of the temperature from 800 °C to 1600 °C in good agreement with experimental results. The physically based formulation gives also a justification of the temperature dependency of the apparent thermal activation energy and of the strain rate sensitivity.</div></div>","PeriodicalId":373,"journal":{"name":"Journal of Nuclear Materials","volume":"616 ","pages":"Article 156083"},"PeriodicalIF":3.2000,"publicationDate":"2025-08-05","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Journal of Nuclear Materials","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0022311525004775","RegionNum":2,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q3","JCRName":"MATERIALS SCIENCE, MULTIDISCIPLINARY","Score":null,"Total":0}
引用次数: 0
Abstract
Modelling of viscoplastic behaviour of nuclear fuel at high temperature is of major interest to analyze the risk of cladding failure in power transient condition where pellet to cladding mechanical interaction occurs. In this study, we investigate the impact of dislocation climbing on the viscoplastic behaviour of single crystal at high temperature where climbing mechanism is activated by vacancy diffusion. The modelling framework is that of an existing crystal plasticity law devoted to thermally activated gliding for lower temperatures. The constitutive equation of the crystal plasticity model are modified in order to add dislocation interaction hardening and stored dislocation recovery. The latter is assessed with dynamic recovery induced by cross slip and static recovery induced by dislocation climbing. A phenomenological model is proposed to compute the dislocation climbing velocity and the associated dislocation density recovery rate. The dislocation gliding velocity law is also improved with a physically based formulation introducing the activation energy for a double kink mechanism. The complete model, for low and high temperatures, is built with a harmonic coupling function enabling a more physically based formulation of the constitutive equations devoted to each mechanism. An implicit numerical implementation of the resulting model is proposed with a finite strain formulation in the framework of the MFront open source tool. A first validation of the complete model has been done with experiment/simulation comparisons for single crystal creep compression tests. In this first step, the validation is limited to orientations where only the modes 1 and 2 (soft and hard slip modes) are suspected of having a major contribution to the viscoplastic behaviour. Thanks to the contribution of dislocation gliding, interaction and climbing we can explain the evolution of the compression flow stress as a function of the temperature from 800 °C to 1600 °C in good agreement with experimental results. The physically based formulation gives also a justification of the temperature dependency of the apparent thermal activation energy and of the strain rate sensitivity.
期刊介绍:
The Journal of Nuclear Materials publishes high quality papers in materials research for nuclear applications, primarily fission reactors, fusion reactors, and similar environments including radiation areas of charged particle accelerators. Both original research and critical review papers covering experimental, theoretical, and computational aspects of either fundamental or applied nature are welcome.
The breadth of the field is such that a wide range of processes and properties in the field of materials science and engineering is of interest to the readership, spanning atom-scale processes, microstructures, thermodynamics, mechanical properties, physical properties, and corrosion, for example.
Topics covered by JNM
Fission reactor materials, including fuels, cladding, core structures, pressure vessels, coolant interactions with materials, moderator and control components, fission product behavior.
Materials aspects of the entire fuel cycle.
Materials aspects of the actinides and their compounds.
Performance of nuclear waste materials; materials aspects of the immobilization of wastes.
Fusion reactor materials, including first walls, blankets, insulators and magnets.
Neutron and charged particle radiation effects in materials, including defects, transmutations, microstructures, phase changes and macroscopic properties.
Interaction of plasmas, ion beams, electron beams and electromagnetic radiation with materials relevant to nuclear systems.