核聚变反应堆用先进F/M钢和散裂靶中H和He的协同作用

IF 2.8 2区 工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY
Yiqihui Lan , Peng Jin , Minghuan Cui , Jing Li , Dongsheng Li , Yushan Yang , Zeyuan Chen , Yuhan Zhai , Wenhui Zhang , Yucheng Feng , Liangting Sun , Tielong Shen , Zhiguang Wang
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引用次数: 0

摘要

对比研究了H和He对两种候选铁素体/马氏体钢(SIMP和T91)的显微组织演变、辐照膨胀和硬化的协同效应。离子辐照实验采用H2+/He2+混合束流,剂量分别为4 × 1017 H2+/cm2和1 × 1017 He2+/cm2,辐照温度分别为RT、300℃和500℃。结果表明,在低温下,H和He相互作用形成稳定的He空位团簇,促进了均匀的空腔成核。随着温度的升高,空洞的分布更加不均匀,特别是在晶界和位错处。值得注意的是,与T91相比,SIMP具有更好的抗辐照膨胀性,这可能是由于其更精细的微观结构和更高的硅含量。研究还表明,SIMP的硬化比T91更为明显,这与位错环的尺寸和密度更大有关。辐照硬化随温度升高而降低。这些发现揭示了H和He之间的温度敏感协同作用,强调了其在聚变和散裂环境下材料设计的重要性。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Synergies between H and He in advanced F/M steels for fusion reactors and spallation target
A comparative study was conducted to investigate the synergistic effects of H and He on the microstructure evolution, irradiation swelling, and hardening of two candidate ferritic/martensitic steels (SIMP and T91) for fusion reactors and spallation target. Ion irradiation experiments were carried out using mixed H2+/He2+ beams with doses of 4 × 1017 H2+/cm2 and 1 × 1017 He2+/cm2, at irradiation temperatures of RT, 300 °C, and 500 °C. The results reveal that at low temperatures, H and He interacted to form stable HHe-vacancy clusters, promoting uniform cavity nucleation. As the temperature increases, the cavities were more heterogeneously distributed, particularly at grain boundaries (GBs) and dislocations. Notably, SIMP exhibited superior resistance to irradiation swelling compared to T91, likely due to its finer microstructure and higher silicon content. The study also shows that the hardening of SIMP was more pronounced than T91, correlating with larger size and higher density of dislocation loops (DLs). The irradiation hardening decreased with increasing temperature. These findings reveal a temperature-sensitive synergy between H and He, emphasizing its significance for material design in fusion and spallation environments.
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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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