Browsing SINTEF Open by Author "Dias, M."
Now showing items 1-4 of 4
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Behavior of Cu-Y2O3 and CuCrZr-Y2O3 composites before and after irradiation
Martins, R.; Antão, F.; Correia, J.B.; Tejado, E.; Pastor, J.; Galatanu, A.; Almeida Carvalho, Patricia; Alves, E.; Dias, M. (Peer reviewed; Journal article, 2023)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. ... -
Damage threshold of CuCrFeTiV high entropy alloys for nuclear fusion reactors
Dias, M.; Magalhães, S.; Antão, F.; da Silva, Silva; Gonçalves, A.P.; Almeida Carvalho, Patricia; Correia, J.B.; Galatanu, A.; Alves, E. (Peer reviewed; Journal article, 2022)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 ... -
Hybrid molecular dynamic Monte Carlo simulation and experimental production of a multi-component Cu–Fe–Ni–Mo–W alloy
Dias, M.; Almeida Carvalho, Patricia; Gonçalves, A.P.; Alves, E.; Correia, J.B. (Peer reviewed; Journal article, 2023)High-entropy alloys are a class of materials intensely studied in the last years due to their innovative properties. Their unconventional compositions and chemical structures hold promise for achieving unprecedented ... -
Stability of beryllium-tungsten coatings under annealing up to 1273 K
Mateus, R.; Porosnicu, C.; Dias, M.; Vitelaru, C.; Almeida Carvalho, Patricia; Lungu, C.P.; Alves, E. (Peer reviewed; Journal article, 2024)Tungsten and beryllium were foreseen to be the plasma facing materials (PFMs) for the first wall and divertor in ITER. Particles eroded from PFMs surfaces will be transported by the plasma and co-deposited in different ...