Qining Zheng , Shuqin Wen , Mingju Chen , Ce Zheng , Guanghai Bai , Jinshan Li , Biao Chen
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Annealing-induced microstructure and mechanical property evolution of helium-irradiated Cr coatings
Post-irradiation annealing (PIA) is a highly effective approach for investigating the impacts of irradiation temperature. In this work, annealing at 350–800 °C was conducted on helium ion irradiated (300 keV, 6.85 × 10¹⁵ ions/cm²) chromium coatings, and the impact of annealing temperature on irradiation defects and mechanical properties of chromium was investigated. A critical temperature threshold of 700 °C (0.45 Tm) was identified, beyond which helium bubbles exhibited a pronounced transition in coarsening behavior: gradual growth below 700 °C transitioned to rapid coarsening dominated by migration-coalescence mechanisms at higher temperatures. Concurrently, grain boundaries emerged as preferential defect sinks, facilitating bubble nucleation and growth. The swelling rate of the coating is primarily governed by bubble size and increases with temperature. Dislocation loops displayed coevolution with helium bubbles, mirroring temperature-dependent growth trends. Irradiation hardening primarily originated from dislocation pinning by both loops and bubbles. Depth-resolved nanoindentation analysis via the Nix-Gao model quantified intrinsic hardness gradients, revealing deviations from theoretical predictions attributed to unaccounted defects below 2 nm and grain-coarsening effects.
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.