Junjie Cao , Liping Guo , Yiheng Chen , Wenbin Lin , Rui Yan , Zixiao Wang , Yunxiang Long
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引用次数: 0
Abstract
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.
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.