4.6 Article

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

Journal

NUCLEAR MATERIALS AND ENERGY
Volume 30, Issue -, Pages -

Publisher

ELSEVIER
DOI: 10.1016/j.nme.2022.101144

Keywords

Copper alloy; Defects; Segregation; Fusion; Radiation damage

Funding

  1. research program of Collaborative Research Station of High-voltage Electron Microscopy by MEXT
  2. [26420850]
  3. [18 K04774]

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The sink strengths of precipitate/matrix interfaces in Cu alloys, especially Cr-rich precipitates, were investigated using high-voltage electron microscopy. The results showed that these interfaces serve as strong sinks for point defects.
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.

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