Haiyu Xue , Te Zhu , Xiangming Xie , Qigui Yang , Peng Zhang , Baoyi Wang , Pinjing Cheng , Xingzhong Cao , Haibiao Wu
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引用次数: 0
摘要
用于聚变能源设施的等离子体材料,如纯钨(W)和钨镍铁(W- ni - fe)合金,必须承受氦辐照,这可能导致纳米裂纹,最终发展为表面起泡和大尺寸裂纹。这一现象背后的机制仍然难以捉摸,因此需要进行详细的调查。本研究采用正电子湮没光谱(PAS)和透射电子显微镜(TEM)对纳米裂纹的形成进行分析。结果表明,氦辐照首先在材料基体中产生空位型缺陷。随着辐照剂量的增加,注入的氦原子被这些空位捕获,导致氦-空位复合物的形成,这些复合物随后膨胀成更大的聚集体,最终演变成氦泡。这些气泡的结合导致高压氦实体的产生,一旦内部压力超过材料的结构极限,这些氦实体就会沉淀纳米裂纹,最终导致表面起泡。
Mechanism of nanocracks formation in tungsten and tungsten-nickel-iron alloy under helium ion irradiation
Plasma-facing materials used in fusion energy facilities, such as pure tungsten (W) and tungsten-nickel-iron (W-Ni-Fe) alloys, must withstand helium irradiation, which can lead to nanocrack that eventually develop into surface blistering and large-size crack. The mechanisms behind this phenomenon remain elusive, highlighting the need for a detailed investigation. This study employed positron annihilation spectroscopy (PAS) and transmission electron microscopy (TEM) to analyze the development of nanocracks. The results elucidate that helium irradiation initially engenders vacancy-type defects within the material matrix. As the irradiation dose escalates, implanted helium atoms are captured by these vacancies, leading to the formation of helium-vacancy complexes that subsequently expand into larger aggregates and eventually evolve into helium bubbles. The coalescence of these bubbles results in the generation of high-pressure helium entities, which precipitate nanocrack formation once the internal pressure surpasses the structural limits of the material, ultimately culminating in surface blistering.
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.