He ion irradiation resistance of W-Ni-Fe alloys with variable Ni and Fe concentrations

• Published in: Fusion engineering and design 2024-05, Vol.202, p.114310, Article 114310
• Main Authors: Liu, Sheng, Zhu, Te, Wang, Zhen, Xue, Haiyu, Zhang, Peng, Yu, Runsheng, Zhang, Qiaoli, Fan, Ping, Yuan, Daqing, Zhao, Guizhi, Cao, Xingzhong, Wu, Haibiao
• Format: Article
• Language: English
• Subjects: He-vacancy complexes; Helium irradiation; Positron annihilation spectroscopy; W-Ni-Fe alloys
• ISSN: 0920-3796; 1873-7196
• DOI: 10.1016/j.fusengdes.2024.114310

•Two W heavy alloys (WHAs) are examined for radiation resistance.•The WHAs have different Fe and Ni concentrations.•Low-dose irradiation inflicts negligible surface damage to both WHAs.•High-dose irradiation causes surface damage, but to a lesser extent than on pure W.•The WHAs have significant potential for application in nuclear materials. Tungsten-nickel-iron (W-Ni-Fe) alloys, commonly known as W heavy alloys (WHAs), exhibit enhanced ductility, thermal conductivity, and mechanical attributes. These properties render WHAs highly suitable as plasma-facing materials in lieu of pure W. This investigation examines the irradiation resistance of two WHAs—97W-2Ni-1Fe and 90W-7Ni-3Fe—by subjecting them to He ion irradiation at doses reaching 5 × 1017 ions/cm2. The study establishes that low-dose irradiation (1 × 1017 ions/cm2) inflicted negligible surface damage on both WHA compositions. Nonetheless, increasing the radiation dose to 5 × 1017 ions/cm2 led to observable surface impairments, albeit at a reduced magnitude when compared to pure W. An array of analytical methods was employed to characterize irradiation-induced microstructures and void swelling, including positron annihilation spectroscopy, thermal desorption spectroscopy, and transmission electron microscopy. These analyses revealed that low-dose irradiated WHAs predominantly generated vacancy-type defects. Moreover, these defects evolved into HemVn and HemVn-NiFe complexes as the irradiation dose increased. Concurrently, He bubble density escalated with rising irradiation dosage. When subjected to an irradiation dose of 1 × 1017 ions/cm2, both alloys manifested desorption levels approximately 6.5 times greater than that observed in pure W. The findings of this investigation offer valuable insights to the understanding of WHA irradiation behavior in nuclear materials.