Anshul Kamboj , Md Minaruzzaman , Kaustubh Bawane , Lingfeng He , Lin Shao , J. Matthew Mann , Marat Khafizov , Yongfeng Zhang , Miaomiao Jin , David H. Hurley , Boopathy Kombaiah
{"title":"高温质子辐照下单晶二氧化钍的缺陷环和完美环演化","authors":"Anshul Kamboj , Md Minaruzzaman , Kaustubh Bawane , Lingfeng He , Lin Shao , J. Matthew Mann , Marat Khafizov , Yongfeng Zhang , Miaomiao Jin , David H. Hurley , Boopathy Kombaiah","doi":"10.1016/j.jnucmat.2025.155955","DOIUrl":null,"url":null,"abstract":"<div><div>Nuclear fuels experience a pronounced microstructural evolution leading to reduction in thermal conductivity, changes in mechanical properties, and impacting their ability to retain fission products in operational environments, significantly affecting reactor’s performance. Such changes result primarily from accumulation of fission products in the form of solid precipitates and inert gas bubbles, and fuel restructuring upon accumulation of radiation-induced defects. Particularly within the realm of radiation damage, the formation and evolution of faulted loops play a critical role in subsequent evolution of dislocations, grain subdivision and recrystallization degrading fuel’s physical properties. This research focused on the dynamics of faulted and perfect loops, alongside the unfaulting process, in single crystal ThO<sub>2</sub> subjected to proton-irradiation at doses of 0.42, 0.62, and 0.74 dpa at 1000 °C. Transmission electron microscopy characterization and cluster dynamics modeling were employed to uncover the mechanisms of nucleation and growth, and unfaulting of faulted loops, which are crucial in driving the evolution of defects. In this study, our findings suggested that the critical diameter for faulted loop unfaulting was approximately 2 nm. Moreover, the rate of unfaulting was found to scale linearly with the dislocation loop density and quadratically with the loop radius from the modeling results, highlighting the intricate dependence of defect evolution on microstructural parameters.</div></div>","PeriodicalId":373,"journal":{"name":"Journal of Nuclear Materials","volume":"615 ","pages":"Article 155955"},"PeriodicalIF":3.2000,"publicationDate":"2025-06-04","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"Faulted and Perfect Loop Evolution in Single Crystal Thorium Dioxide under High-Temperature Proton Irradiation\",\"authors\":\"Anshul Kamboj , Md Minaruzzaman , Kaustubh Bawane , Lingfeng He , Lin Shao , J. Matthew Mann , Marat Khafizov , Yongfeng Zhang , Miaomiao Jin , David H. Hurley , Boopathy Kombaiah\",\"doi\":\"10.1016/j.jnucmat.2025.155955\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><div>Nuclear fuels experience a pronounced microstructural evolution leading to reduction in thermal conductivity, changes in mechanical properties, and impacting their ability to retain fission products in operational environments, significantly affecting reactor’s performance. Such changes result primarily from accumulation of fission products in the form of solid precipitates and inert gas bubbles, and fuel restructuring upon accumulation of radiation-induced defects. Particularly within the realm of radiation damage, the formation and evolution of faulted loops play a critical role in subsequent evolution of dislocations, grain subdivision and recrystallization degrading fuel’s physical properties. This research focused on the dynamics of faulted and perfect loops, alongside the unfaulting process, in single crystal ThO<sub>2</sub> subjected to proton-irradiation at doses of 0.42, 0.62, and 0.74 dpa at 1000 °C. Transmission electron microscopy characterization and cluster dynamics modeling were employed to uncover the mechanisms of nucleation and growth, and unfaulting of faulted loops, which are crucial in driving the evolution of defects. In this study, our findings suggested that the critical diameter for faulted loop unfaulting was approximately 2 nm. 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Faulted and Perfect Loop Evolution in Single Crystal Thorium Dioxide under High-Temperature Proton Irradiation
Nuclear fuels experience a pronounced microstructural evolution leading to reduction in thermal conductivity, changes in mechanical properties, and impacting their ability to retain fission products in operational environments, significantly affecting reactor’s performance. Such changes result primarily from accumulation of fission products in the form of solid precipitates and inert gas bubbles, and fuel restructuring upon accumulation of radiation-induced defects. Particularly within the realm of radiation damage, the formation and evolution of faulted loops play a critical role in subsequent evolution of dislocations, grain subdivision and recrystallization degrading fuel’s physical properties. This research focused on the dynamics of faulted and perfect loops, alongside the unfaulting process, in single crystal ThO2 subjected to proton-irradiation at doses of 0.42, 0.62, and 0.74 dpa at 1000 °C. Transmission electron microscopy characterization and cluster dynamics modeling were employed to uncover the mechanisms of nucleation and growth, and unfaulting of faulted loops, which are crucial in driving the evolution of defects. In this study, our findings suggested that the critical diameter for faulted loop unfaulting was approximately 2 nm. Moreover, the rate of unfaulting was found to scale linearly with the dislocation loop density and quadratically with the loop radius from the modeling results, highlighting the intricate dependence of defect evolution on microstructural parameters.
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.