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Effect of W-Cu joining on D transport behavior in plasma-facing components for fusion reactors
In future fusion reactors, W-Cu joining technology will be utilized to fabricate plasma facing components (PFCs). In this study, hydrogen isotope gas-driven permeation (GDP) and thermal desorption spectrometry (TDS) are performed for W-Cu, W and Cu samples to understand the impact of W-Cu joining on fuel transport. GDP results reveal that the diffusion activation energy of the W-Cu sample is 0.289 eV, significantly smaller than that of the reference sample. Compared with the reference sample, the deuterium (D) retention in the W-Cu sample is doubled. High resolution transmission electron microscope (HRTEM) images indicate the presence of a mixed region of about 20 nm at the W-Cu interface, with a dislocation density in this region of 7.38 × 1016 m−2, three orders of magnitude higher than that in W and Cu. Simultaneously, energy dispersive spectrometer (EDS) data show that significant oxygen (O) impurities within the mixed region. Results from first principles simulations suggest that the presence of O at the interface can significantly alter the formation energy of H. The mixed layer not only serves as a diffusion barrier but also has the capacity to capture D. The presence of a high number of dislocations and O impurities in the mixed layer greatly impacts D transport in the W-Cu component.
Effect of W-Cu joining on D transport behavior in plasma-facing components for fusion reactors
In future fusion reactors, W-Cu joining technology will be utilized to fabricate plasma facing components (PFCs). In this study, hydrogen isotope gas-driven permeation (GDP) and thermal desorption spectrometry (TDS) are performed for W-Cu, W and Cu samples to understand the impact of W-Cu joining on fuel transport. GDP results reveal that the diffusion activation energy of the W-Cu sample is 0.289 eV, significantly smaller than that of the reference sample. Compared with the reference sample, the deuterium (D) retention in the W-Cu sample is doubled. High resolution transmission electron microscope (HRTEM) images indicate the presence of a mixed region of about 20 nm at the W-Cu interface, with a dislocation density in this region of 7.38 × 1016 m−2, three orders of magnitude higher than that in W and Cu. Simultaneously, energy dispersive spectrometer (EDS) data show that significant oxygen (O) impurities within the mixed region. Results from first principles simulations suggest that the presence of O at the interface can significantly alter the formation energy of H. The mixed layer not only serves as a diffusion barrier but also has the capacity to capture D. The presence of a high number of dislocations and O impurities in the mixed layer greatly impacts D transport in the W-Cu component.
Effect of W-Cu joining on D transport behavior in plasma-facing components for fusion reactors
Xue-Chun Li (Autor:in) / Hai-Shan Zhou (Autor:in) / Xin-Dong Pan (Autor:in) / Cai-Bin Liu (Autor:in) / Zi-Han Tao (Autor:in) / Hao-Dong Liu (Autor:in) / Guang-Nan Luo (Autor:in)
2024
Aufsatz (Zeitschrift)
Elektronische Ressource
Unbekannt
Metadata by DOAJ is licensed under CC BY-SA 1.0
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