Elisa Cappellari , Davide Pizzocri , Giovanni Zullo , Giovanni Nicodemo , Paul Van Uffelen , Arndt Schubert , Sophie Deanesi , Lelio Luzzi
{"title":"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","authors":"Elisa Cappellari , Davide Pizzocri , Giovanni Zullo , Giovanni Nicodemo , Paul Van Uffelen , Arndt Schubert , Sophie Deanesi , Lelio Luzzi","doi":"10.1016/j.jnucmat.2025.156116","DOIUrl":null,"url":null,"abstract":"<div><div>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 UO<sub>2</sub> 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.</div></div>","PeriodicalId":373,"journal":{"name":"Journal of Nuclear Materials","volume":"617 ","pages":"Article 156116"},"PeriodicalIF":3.2000,"publicationDate":"2025-09-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"On a physics-based model of grain-boundary bubbles overpressurisation and its effects on fuel fragmentation\",\"authors\":\"Elisa Cappellari , Davide Pizzocri , Giovanni Zullo , Giovanni Nicodemo , Paul Van Uffelen , Arndt Schubert , Sophie Deanesi , Lelio Luzzi\",\"doi\":\"10.1016/j.jnucmat.2025.156116\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><div>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 UO<sub>2</sub> 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.</div></div>\",\"PeriodicalId\":373,\"journal\":{\"name\":\"Journal of Nuclear Materials\",\"volume\":\"617 \",\"pages\":\"Article 156116\"},\"PeriodicalIF\":3.2000,\"publicationDate\":\"2025-09-15\",\"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/S0022311525005100\",\"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}","platform":"Semanticscholar","paperid":null,"PeriodicalName":"Journal of Nuclear Materials","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0022311525005100","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}
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.
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.