Analysis of hardening limits of oxide dispersion strengthened steel
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In the quest of materials for the first wall of the future fusion reactor, it has been shown that oxide dispersion strengthened (ODS) ferritic / martensitic (F/M) steels appear to be promising candidates. The inherent good mechanical properties supported b ...
The effects of neutron irradiation on austenitic stainless steels, usually used for the manufacturing of internal elements of nuclear reactors (e.g. the core shrouds), are the alteration of the microchemistry and the microstructure, and, as a consequence, ...
Nanocrystalline metals have been an area of great interest in recent years due to their enhanced characteristics. One of the most striking is implied by the Hall-Petch relation: with decreasing grain size the material becomes stronger. This promise is fulf ...
TiAl is a well known high temperature material with good creep properties. It is investigated as a potential structural material for Generation IV high temperature gas cooled nuclear reactors. The tests are performed with the ABB-2 (Ti-rich TiAl with 2 at. ...
Oxide dispersion strengthened steels based on the ferritic/martensitic steel EUROFER97 are developed. The reinforcing particles dispersed in the matrix of EUROFER97 are made of yttria and yttrium titanium oxides. Microstructure is investigated by transmiss ...
The effects of neutron irradiation on the microstructure of welded joints made of austenitic stainless steels have been investigated. The materials were welded AISI 304 and AISI 347, so-called test weld materials, and irradiated with neutrons at 300 degree ...
The in situ matrix flow stress of continuous fibre-reinforced aluminium is measured in tension along the fibre axis. We use a new, tighter, estimate for the effect differential Poisson contraction between fibres and matrix and take into consideration nonli ...
In this study, the tensile and fracture properties and the microstructure of the reduced-activation tempered martensitic steel Eurofer97 have been investigated. This technical alloy is a 9%Cr steel developed within the European fusion material research pro ...
Nuclear materials have been successfully employed in commercial fission reactors for many decades. Research and material development for advanced fission system and future thermo-nuclear fusion reactors have acquired maturity while great challenges remain ...
The strain-hardening behaviour of a tempered martensitic iron-chromium-carbon model was examined in terms of dislocation mechanics. Tensile tests of this body-centered cubic alloy were carried out from 77 up to 293 K. A specific relationship between the fl ...