基于物理模型的颗粒边界气泡超压及其对燃料破碎的影响

IF 3.2 2区 工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY
Elisa Cappellari , Davide Pizzocri , Giovanni Zullo , Giovanni Nicodemo , Paul Van Uffelen , Arndt Schubert , Sophie Deanesi , Lelio Luzzi
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引用次数: 0

摘要

充气气泡和孔隙的过压被认为是氧化物燃料碎裂和裂变气体在瞬态期间释放到辐照燃料的无棒体积中的主要驱动因素。在此框架下,裂变气体行为的先进建模对于提高燃料性能代码的预测能力至关重要。本研究开发了一个基于物理的UO2燃料中晶界裂变气体释放模型,并将其实现到SCIANTIX中,SCIANTIX是米兰理工大学开发的一个开源代码,用于模拟核燃料中的裂变气体行为。该模型首先利用辐照燃料的数据,描述了颗粒表面通过连续气泡网络释放的气体。然后将重点放在损坏晶界的气体释放上,应用断裂力学来预测气泡过压引起的微裂纹。利用ABAQUS软件进行有限元模拟,以评估气泡密度、形状和大小对应力强度的影响。该模型通过三个独立效应实验数据集进行了评估,包括退火测试和通过扫描电子显微镜观察颗粒表面,证明了气体膨胀和裂变气体释放的有希望的预测能力。这项工作为通过基于物理的方法改进裂变气体行为建模提供了一个有价值的工具,并为未来扩展到高燃烧结构奠定了基础,为更全面地描述燃料碎片提供了一个框架。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
On a physics-based model of grain-boundary bubbles overpressurisation and its effects on fuel fragmentation
Overpressurisation of gas-filled bubbles and pores is considered the main driver of oxide fuel fragmentation and fission gas release into the rod free volume of irradiated fuel during transients. In this framework, advanced modelling of fission gas behaviour is crucial to enhance the predictive capabilities of fuel performance codes. This study develops a physics-based model for fission gas release from grain boundaries in UO2 fuel and implements it into SCIANTIX, an open-source code developed at Politecnico di Milano to simulate fission gas behaviour in nuclear fuels. The model first describes gas release through continuous bubble networks at the grain face, exploiting data from irradiated fuel. It then focuses on gas release from damaged grain boundaries, applying fracture mechanics to predict micro-cracking induced by bubble overpressurisation. Finite elements simulations are performed using ABAQUS software, in order to assess stress intensification as a function of bubble density, shape, and size. The model is assessed against three separate-effect experiment datasets, including annealing tests and grain-face observations via scanning electron microscopy, demonstrating promising predictive capabilities for gaseous swelling and fission gas release. This work provides a valuable tool for improving fission gas behaviour modelling through a physics-based approach and lays the groundwork for future extensions to the high burn-up structure, offering a framework for a more comprehensive description of fuel fragmentation.
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来源期刊
Journal of Nuclear Materials
Journal of Nuclear Materials 工程技术-材料科学:综合
CiteScore
5.70
自引率
25.80%
发文量
601
审稿时长
63 days
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.
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