In-situ observation of damage structure in Cu-Cr-Zr and Cu-Cr alloy during 1.25 MeV electron irradiation

Nuclear Materials and Energy

T. Yamamoto¹  M. Hatakeyama²  K. Sato³  K. Yasunaga⁴  K. Yasuda⁴  S. Matsumura⁴ 

[1] Corresponding author at: 3190 Gofuku, Toyama 930-8555, Japan.;Graduate School of Science and Engineering for Research, University of Toyama, 3190 Gofuku, Toyama-shi, Toyama 930-8555, Japan;Research and Development Department, The Wakasa Wan Energy Research Center, 64-52-1 Nagatani, Turuga-shi, Fukui 914-0192, Japan;Ultramicroscopy Research Center, Department of Applied Quantum Physics and Nuclear Engineering, Kyushu University, Fukuoka 819-0395, Japan;

关键词: Copper alloy;    Defects;    Segregation;    Fusion;    Radiation damage;   

DOI  :  

来源: DOAJ

【 摘 要 】

The sink strengths of precipitate/matrix interfaces in Cu alloys, were investigated by performing in-situ observation of electron irradiation in high-voltage electron microscopy (HVEM). Fine black spot defects, which seemed to be dislocation loops were observed at irradiation temperature ranging between RT and 373 K in Cu–Cr–Zr, Cu–Cr and GlidCop Al–60 alloys with low number density. In Cu–Cr, loops formed on a part of precipitates interfaces. Hence, a part of precipitate/matrix interfaces is a sink with interstitial bias. Whereas, most of the interfaces are neutral sinks for point defects. In the case of Cu–Cr–Zr and GlidCop Al–60, black spots formed around dislocation, which were induced during two-step heat treatment. The results showed that the precipitate/matrix interface of Cr-rich precipitates in Cu alloys serve as a strong sink for point defects.

【 授权许可】

Unknown