三束辐照对腔体演化的温度效应

IF 2.8 2区 工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY
Junjie Cao , Liping Guo , Yiheng Chen , Wenbin Lin , Rui Yan , Zixiao Wang , Yunxiang Long
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引用次数: 0

摘要

为了解聚变中子辐照降低活化铁素体/马氏体(RAFM)钢时辐照损伤与氦、氢转化的协同效应,在受控条件下对中国低活化马氏体(CLAM)钢进行了Fe+H+He三束同时辐照。实验在350°C、450°C和550°C三个温度下进行,每个温度下辐照剂量分别为11 dpa、22 dpa和33 dpa, He比为11 appm/dpa, H比为44 appm/dpa。在350℃时,膨胀的增加归因于氦气泡的数量密度的增加。在450℃时,氦气泡密度在11 ~ 22 dpa之间达到饱和,在偏压驱动机制下转变为空腔生长,最终形成最大的空腔。550℃时,高温抑制了空洞的数量密度,而热辐射限制了空洞的生长速度。随着剂量的增加,由于氦的气泡-空洞转变和尺寸对生长速率的影响,尺寸分布逐渐由单峰向多峰过渡,这一现象在温度越高时越明显。在350°C、450°C和550°C三个温度下,CLAM钢分别经历辐照硬化、最小变化和辐照软化,硬度变化与辐照膨胀密切相关。结果表明,在辐照损伤、氦、氢的协同作用下,辐照缺陷和溶胀的演化。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Temperature effect on cavity evolution by triple-beam irradiation
To understand the synergistic effects of irradiation damage and transmuted helium and hydrogen in reduced-activation ferritic/martensitic (RAFM) steels irradiated by fusion neutrons, China low-activation martensitic (CLAM) steel was subjected to Fe+H+He triple-beam simultaneous irradiation under controlled conditions. The experiments were conducted at three temperatures of 350 °C, 450 °C and 550 °C, with irradiation doses of 11 dpa, 22 dpa and 33 dpa applied at each temperature, maintaining the He ratio of 11 appm/dpa and H ratio of 44 appm/dpa. At 350 °C, the increase in swelling was attributed to an increase in the number density of helium bubbles. At 450 °C, the helium bubble density saturated between 11 and 22 dpa, transitioning to cavities growing under bias-driven mechanisms, ultimately resulting in the formation of the largest voids. At 550 °C, the high temperature suppressed the number density of cavities, while thermal emission limited the void growth rate. With increasing doses, the size distribution gradually transitioned from unimodal to multimodal due to helium bubble-to-void transformation and the influence of size on growth rates, a phenomenon more pronounced at higher temperatures. At the three temperatures of 350 °C, 450 °C and 550 °C, CLAM steel experienced irradiation hardening, minimal changes, and irradiation softening, respectively, with hardness variations closely related to irradiation swelling. The results revealed the evolution of irradiation-induced defects and swelling under the synergistic effect among irradiation damage, helium and hydrogen.
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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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