具有外源性位错的低角度晶界对氢在钨中的保留和输运的影响

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Fusion Engineering and Design Pub Date : 2025-04-01 Epub Date: 2025-02-18 DOI:10.1016/j.fusengdes.2025.114866
Bang An , Yingchong Xu , Hongxian Xie
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引用次数: 0

摘要

氢的保留和输运是关系到未来聚变反应堆安全运行的两个关键问题,而晶体缺陷在这两个问题中起着关键作用。本文采用分子动力学方法研究了具有外源性位错的低角晶界对钨中氢的保留和输运的影响。具有外源性位错的低角晶界应力场可以看作是位错偶极子应力场与位错应力场的叠加,在低角晶界周围形成长程应力场。H的相互作用能图表明,负偏斜核的位错是所有位错中H最有效的捕获位点,动态模拟进一步证实了这一点。最后,通过计算H沿位错线的扩散系数和能垒,研究了低角度晶界的H输运能力,发现负斜向核位错也是H输运的有效纳米通道。本研究为我们提供了对H在钨中的保留和输运的深入了解。
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The effect of low-angle grain boundary with extrinsic dislocation on hydrogen retention and transportation in Tungsten
Hydrogen (H) retention and transportation are two critical issues relating to the safe operation of future fusion reactors, and the crystal defects play key roles in the two issues. In the present work the effect of low-angle grain boundary with extrinsic dislocation on H retention and transport in tungsten was investigated using molecular dynamics method. The stress fields of low-angle grain boundary with extrinsic dislocation can be deemed as superposition of the stress field of a disclination dipole and that of the dislocations, resulting in long-range stress field around the low-angle grain boundary. Interaction energy map of H reveals that the dislocation at the negative disclination core can serve as the most efficient trapping site for H among all the dislocations, which is further confirmed by dynamic simulation. Finally, H transportation capability of the low-angle grain boundary was studied by calculation of diffusion coefficients and energy barriers of H along dislocation lines, it is found that the dislocation at the negative disclination core is also an efficient nanochannel for H transportation. The present work provided us a deep insight into H retention and transport in tungsten.
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来源期刊
Fusion Engineering and Design
Fusion Engineering and Design 工程技术-核科学技术
CiteScore
3.50
自引率
23.50%
发文量
275
审稿时长
3.8 months
期刊介绍: The journal accepts papers about experiments (both plasma and technology), theory, models, methods, and designs in areas relating to technology, engineering, and applied science aspects of magnetic and inertial fusion energy. Specific areas of interest include: MFE and IFE design studies for experiments and reactors; fusion nuclear technologies and materials, including blankets and shields; analysis of reactor plasmas; plasma heating, fuelling, and vacuum systems; drivers, targets, and special technologies for IFE, controls and diagnostics; fuel cycle analysis and tritium reprocessing and handling; operations and remote maintenance of reactors; safety, decommissioning, and waste management; economic and environmental analysis of components and systems.
期刊最新文献
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