Detalhes do Documento

Damage threshold of CuCrFeTiV high entropy alloys for nuclear fusion reactors

Autor(es): Dias, Marta ; Magalhães, S. ; Antão, Francisco ; Silva, R.C. da ; Gonçalves, António Pereira ; Carvalho, Patricia Almeida ; Correia, J.B. ; Galatanu, Andrei ; Alves, E.

Data: 2022

Identificador Persistente: http://hdl.handle.net/10400.9/3921

Origem: Repositório do LNEG

Assunto(s): High entropy alloys; Interlayer; Microstructures


Descrição

ABSTRACT: A CuCrFeTiV high entropy alloy was prepared and irradiated with swift heavy ions in order to check its adequacy for use as a thermal barrier in future nuclear fusion reactors. The alloy was prepared from the elemental powders by ball milling, followed by consolidation by spark plasma sintering at 1178 K and 65 MPa. The samples were then irradiated at room temperature with 300 keV Ar+ ions with fluences in the 3 x 1015 to 3 x 1018 Ar+/cm2 range to mimic neutron-induced damage accumulation during a duty cycle of a fusion reactor. Structural changes were investigated by X-ray diffraction, and scanning electron microscopy and scanning transmission electron microscopy, both coupled with X-ray energy dispersive spectroscopy. Surface irradiation damage was detected for high fluences (3 x 1018 Ar+/cm2) with formation of blisters of up to 1 mu m in diameter. Cross-sectional scanning transmission electron microscopy showed the presence of intergranular cavities only in the sample irradiated with 3 x 1018 Ar+/cm2, while all irradiation experiments produced intragranular nanometric-sized bubbles with increased density for higher Ar+ fluence. The Williamson-Hall method revealed a decrease in the average crystallite size and an increase in residual strain with increasing fluence, consistent with the formation of Ar+ bubbles at the irradiated surface.

Tipo de Documento Artigo científico
Idioma Inglês
Contribuidor(es) Repositório do LNEG
Licença CC
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