Yuzhang Li , Xuejiao Wang , Aidong Lan , Junwei Qiao
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引用次数: 0
Abstract
Refractory high-entropy alloys (RHEAs) have emerged as the focus in the development of the first wall materials for advanced nuclear energy systems due to their outstanding high-temperature properties and irradiation resistance. However, there remains of profound research and model on the irradiation hardening behavior of refractory high-entropy alloys. In this study, Ti1.5ZrHf0.5Nb0.5Ta0.5 RHEA was subjected to 160 keV room-temperature helium ion irradiation at the doses of 0.1 dpa, 1 dpa, and 3 dpa, then the irradiation hardening behavior was analyzed by nanoindentation experiments. The results indicate that the alloys not only exhibit good strength-ductility synergy at room temperature but also possesses excellent resistance to irradiation hardening. X-ray diffraction (XRD) analysis revealed that the alloy maintained a single-phase body-centered cubic (BCC) structure after irradiation. The lattice constant exhibits an initial decrease at 0.1 dpa followed by an increase from 1 dpa to 3dpa. This is attributed to the competition between lattice relaxation and defect volume expansion. The alloys exhibited a hardening of 34.33% at the maximum irradiation dose. We utilize the plastic zone proportion factor f to reflect the plastic localization caused by irradiation defects. This factor is defined as the ratio of the radius of the plastic zone beneath the indenter after irradiation to the radius before irradiation. By separating the contribution of irradiation hardening using an irradiation hardening model, the plastic zone proportion factor f of the nanoindentation testing decreased from 1.65 to 1.32, suggesting that the increase in irradiation defects hindered the expansion of the plastic deformation volume in the alloy. Consequently, the peak of irradiation hardening shifts towards deeper depths. This study could provide an effective reference for quantifying the irradiation hardening behavior of refractory high-entropy alloys.
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.