Study of thermal diffusivity degradation on Cu-OFE copper due to proton and self-ion irradiation using in situ transient grating spectroscopy

IF 3.2 2区 工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY Journal of Nuclear Materials Pub Date : 2025-03-01 Epub Date: 2025-02-05 DOI:10.1016/j.jnucmat.2025.155674
Emmanouil Trachanas , Angus Wylie , Andrea Bignami , Nikolaos Gazis , Michael P. Short , Katrin Michel , Carl Alwmark , Evangelos Gazis , Georgios Fikioris , Håkan Danared
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Abstract

The operation of next-generation particle accelerator facilities with increased beam power parameters and emphasis on performance and reliability signifies the need for experimental studies on material property degradation. Literature is particularly scarce regarding the effects of ionizing radiation damage on cavity components at applicable radiation conditions, with even less extant work studying the effect of simultaneous irradiation on primary materials and their physical properties such as thermal transport. This study presents the impact on thermal diffusivity in oxygen-free electronic Cu-OFE specimens due to proton and self-ion (Cu3+) irradiation. Copper samples with the exactly same processing route as the bulk material for European Spallation Source (ESS) Radio-Frequency Quadrupole (RFQ) were characterized with scanning electron microscopy (SEM), X-ray diffraction (XRD) and electron backscatter diffraction (EBSD), followed by irradiation at room temperature with protons and self-ions (Cu3+) with fluences up to 4.25 × 1017 p/cm2 and 1.10×1015 ions/cm2, 1.69×1015 ions/cm2 respectively. In situ ion irradiation transient grating spectroscopy (I3TGS) was used in order to monitor radiation-induced changes in thermal diffusivity in real time. The results indicate a significant thermal diffusivity drop only after the proton irradiation (10.86%) in contrast to the results obtained for self-ions (Cu3+) where no significant changes (3%) are reported. The results are compared with existing literature and correlated with the nature of post-irradiation defect structures based on the particle type. In the case of protons the contribution of hydrogen implantation in stabilization of defects and on the reduction of thermal diffusivity is discussed. I3TGS in combination with concurrent ion irradiation offers a powerful online diagnostic tool for the evaluation of the impact of operational parameters in particle accelerator components.
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用原位瞬态光栅光谱研究质子和自离子辐照对Cu-OFE铜热扩散率的影响
随着新一代粒子加速器设备的运行,束流功率参数的增加以及对性能和可靠性的重视,表明需要对材料性能退化进行实验研究。在适用的辐射条件下,关于电离辐射损伤对腔体成分影响的文献特别少,而研究同时辐照对原始材料及其物理性质(如热输运)的影响的文献就更少了。研究了质子和自离子(Cu3+)辐照对无氧电子Cu-OFE试样热扩散率的影响。采用与欧洲散裂源(ESS)射频四极杆(RFQ)本体材料完全相同的工艺流程,采用扫描电镜(SEM)、x射线衍射(XRD)和电子背散射衍射(EBSD)对铜样品进行了表征,并在室温下分别用影响高达4.25 × 1017 p/cm2和1.10×1015 ions/cm2、1.69×1015 ions/cm2的质子和自离子(Cu3+)进行了辐照。采用原位离子辐照瞬态光栅光谱(I3TGS)实时监测辐射引起的热扩散系数变化。结果表明,仅在质子辐照后,热扩散率才显著下降(10.86%),而自离子(Cu3+)的结果则没有显著变化(约3%)。结果与现有文献进行了比较,并根据粒子类型与辐照后缺陷结构的性质进行了关联。在质子的情况下,讨论了氢注入对缺陷稳定和热扩散率降低的贡献。I3TGS与同步离子辐照相结合,为评估粒子加速器组件中运行参数的影响提供了一个强大的在线诊断工具。
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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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