Hucheng Yu , Yuanyuan Dong , Ziqi Cao , Yifan Ding , Xiaotong Wang , Jiyong Huang , Guang Ran
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引用次数: 0
Abstract
To better understand the evolution of dislocation loops in RPV steel at different temperatures, in-situ irradiation experiments of 400 keV Fe+were conducted using a RPV model alloy Fe–1.0Mn–0.7Ni–0.2Si (wt.%) at 240 °C, 350 °C, 450 °C, and 550 °C. The nucleation rate of dislocation loops increases first and then decreases with the increase of irradiation dose when T < 550 °C. The lower the temperature, the higher the nucleation rate of dislocation loop. The relationships between the average size & number density of dislocation loops and damage dose, as well as irradiation temperatures, is analyzed. The data indicate that higher irradiation temperatures result in larger loops with lower density. This is most evident at 550 °C, where both the average size and number density of dislocation loops vary significantly. Furthermore, quantitative analysis of the proportion of ½<111> and 〈100〉 dislocation loops at different temperatures reveals that when the temperature increases from 450 °C to 550 °C, the proportion of 〈100〉 loops decreases, for example, from 42 % to 25 % at 3.0 dpa. Moreover, the irradiation hardening induced by dislocation loops generally decreases with increasing temperature. These findings offer novel insights into the irradiation damage mechanisms in RPV steel.
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.