Behavior of Cu-Y2O3 and CuCrZr-Y2O3 composites before and after irradiation

• Autor(a) principal: Martins, Ricardo
• Data de Publicação: 2023
• Outros Autores: Antão, Francisco, Correia, J.B., Tejado, Elena, Pastor, Jose Ygnacio, Galatanu, A., Almeida Carvalho, Patricia, Alves, E., Dias, Marta
• Tipo de documento: Artigo
• Idioma: eng
• Título da fonte: Repositório Científico de Acesso Aberto de Portugal (Repositórios Cientìficos)
• Texto Completo: http://hdl.handle.net/10400.9/4162
• topic: Materials; Composites; Spark plasma sintering; Thermal diffusivity; Densification; Mechanical properties; Thermal barriers

ABSTRACT: The Cu-Y2O3 and CuCrZr-Y2O3 materials have been devised as thermal barriers in nuclear fusion reactors. It is expected that in the nuclear environments, the materials should be working on extreme conditions of irradiation. In this work the Cu-Y2O3 and CuCrZr-Y2O3 were prepared and then irradiated in order to understand the surface irradiation resistance of the material. The composites were prepared in a glove box and consolidated with spark plasma sintering. The microstructures revealed regions of Y2O3 dispersion and Y2O3 agglomerates both in the Cu matrix and in the CuCrZr. The irradiated samples did not show any surface modification indicating that the materials seem to be irradiation resistant in the present situation. The thermal conductivity values for all the samples measured are lower than pure Cu and higher than pure W, however are higher than those expected, and therefore, the application of these materials as thermal barriers is compromised.