温度对RPV模型钢位错环演化的影响:原位Fe+辐照

IF 3.2 2区 工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY
Hucheng Yu , Yuanyuan Dong , Ziqi Cao , Yifan Ding , Xiaotong Wang , Jiyong Huang , Guang Ran
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引用次数: 0

摘要

为了更好地了解不同温度下RPV钢中位错环的演变,使用RPV模型合金Fe - 1.0 mn - 0.7 ni - 0.2 si (wt.%)进行了400 keV Fe+在240°C、350°C、450°C和550°C的原位辐照实验。当温度为550℃时,随着辐照剂量的增加,位错环的成核速率先增大后减小。温度越低,位错环的成核速率越高。分析了位错环的平均尺寸和数目密度与损伤剂量和辐照温度的关系。数据表明,较高的辐照温度会导致较大的环密度较低。这在550°C时最为明显,位错环的平均尺寸和数量密度都有显著变化。此外,对不同温度下½<;111>;和< 100 >位错环的比例进行定量分析表明,当温度从450℃升高到550℃时,< 100 >位错环的比例下降,例如在3.0 dpa时,从42%下降到25%。此外,位错环引起的辐照硬化一般随温度升高而降低。这些发现为RPV钢的辐照损伤机制提供了新的见解。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Effect of temperature on dislocation loop evolution in RPV model steel: In-situ Fe+ irradiation
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.
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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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