Fei Sun , Xiangming Lin , Yijin Huang , Jipeng Zhu , Long Cheng , Yifan Zhang , Hai-Shan Zhou , Lai-Ma Luo , Yasuhisa Oya , Yucheng Wu
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引用次数: 0
Abstract
In fusion environments, plasma-facing materials are subjected to the bombardment by high-energy neutrons and large fluxes plasmas, resulting in the formation of numerous irradiation defects. These defects act as trapping sites for fuel hydrogen isotopes, increasing the tritium retention. Under thermal loads at high temperatures, these defects undergo dynamic changes, leading to complex effects on hydrogen isotope transport behaviors. Understanding the evolution of defects at different temperatures and elucidating their impact on hydrogen isotope retention is essential. In this work, a dynamic evolution model of typical vacancy defects and their clusters was constructed based on rate theory and integrated into the hydrogen isotope transport model. The simulation results were compared with experimental data, showing a good agreement between the two. Further results indicated that increasing the annealing temperature reduces defect concentrations. At high temperatures, large vacancy clusters dissociate into smaller ones, with some smaller clusters annihilating and others associating to form larger clusters. In addition, the processes of vacancy clusters association and dissociation dominate this evolution. Regarding hydrogen isotope retention, defect evolution affects the concentration of deuterium (D) atoms within the material. After D is introduced into tungsten, the concentration of D corresponds to the concentration of vacancy clusters. It is found that during thermal desorption, the desorption peak corresponding to the largest vacancy clusters is more pronounced, while other clusters show less significant peaks. This is because some of the D atoms de-trapped from the vacancy clusters are released to the material surface, while others are re-trapped by larger vacancy clusters. The findings of this work will contribute to a more accurate assessment of hydrogen isotope retention under defect dynamic evolution in future fusion reactors.
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.