International audienceFerritic-martensitic Oxide Dispersion Strengthened (ODS) steels are potential materials for fuel pin cladding in Sodium Fast Reactor (SFR) and their optimisation is essential for future industrial applications. In this paper, a feasibility study concerning the generation of tensile specimens using a quenching dilatometer is presented. The ODS steel investigated contains 9%Cr and exhibits a phase transformation between ferrite and austenite around 870°C. The purpose was to generate different microstructures and to evaluate their tensile properties. Specimens were machined from a cladding tube and underwent controlled heat treatments inside the dilatometer. The microstructures were observed using Electron Backscatter Dif...
The 9Cr-ODS martensitic steel claddings were developed by cold-rolling and subsequent heat-treatment...
This project is dedicated to the development of fuel cladding materials for Gen-IV Sodium-cooled Fas...
Fe-Cr based oxide dispersion strengthened (ODS) alloys are potential candidates for usage as nuclear...
International audienceFerritic-martensitic Oxide Dispersion Strengthened (ODS) steels are potential ...
International audienceFerritic-martensitic Oxide Dispersion Strengthened (ODS) steels are potentialm...
International audienceOxide Dispersion Strengthened ferritic/martensitic steels are developed as fut...
International audienceOxide Dispersion Strengthened (ODS) steels envisaged as cladding materials in ...
Oxide dispersion strengthened (ODS) steel is expected as high-performance structural components unde...
International audienceA new martensitic ODS alloy (nominal composition Fe-9Cr-1W-0.2Ti-0.3Y2O3) has ...
International audienceThe development of generation IV nuclear reactor requires improvements in stru...
International audienceOxide dispersion strengthened (ODS) ferritic steels are promising candidates f...
The 9Cr-ODS martensitic steel claddings were developed by cold-rolling and subsequent heat-treatment...
This project is dedicated to the development of fuel cladding materials for Gen-IV Sodium-cooled Fas...
Fe-Cr based oxide dispersion strengthened (ODS) alloys are potential candidates for usage as nuclear...
International audienceFerritic-martensitic Oxide Dispersion Strengthened (ODS) steels are potential ...
International audienceFerritic-martensitic Oxide Dispersion Strengthened (ODS) steels are potentialm...
International audienceOxide Dispersion Strengthened ferritic/martensitic steels are developed as fut...
International audienceOxide Dispersion Strengthened (ODS) steels envisaged as cladding materials in ...
Oxide dispersion strengthened (ODS) steel is expected as high-performance structural components unde...
International audienceA new martensitic ODS alloy (nominal composition Fe-9Cr-1W-0.2Ti-0.3Y2O3) has ...
International audienceThe development of generation IV nuclear reactor requires improvements in stru...
International audienceOxide dispersion strengthened (ODS) ferritic steels are promising candidates f...
The 9Cr-ODS martensitic steel claddings were developed by cold-rolling and subsequent heat-treatment...
This project is dedicated to the development of fuel cladding materials for Gen-IV Sodium-cooled Fas...
Fe-Cr based oxide dispersion strengthened (ODS) alloys are potential candidates for usage as nuclear...