International audienceDevelopment of fast-neutron sodium-cooled Generation IV reactors is resulting in extremely severe environment conditions for cladding tubes [1]. Both temperature and irradiation level will increase compared to the nowadays conditions. Due to their characteristics in irradiated environment, the oxide dispersion strengthened (ODS) ferritic and martensitic steels are natural candidate cladding materials[2]. However, they exhibit low deformation capabilities at room temperature, leading to problematic issues for forming such as pilgering. In order to improve the fabrication route for tubes, both metallurgical and numerical approaches can be conducted [3,4,5]. To reach predictive description of damage location and evolution...
International audienceOxides Dispersed strengthened (ODS) stainless steels are foreseen for fuel cla...
Oxide Dispersion Strengthened ferritic/martensitic alloys are developed as prospective cladding mate...
International audienceOxide dispersion strengthened (ODS) steels are suitable candidates for claddin...
International audienceDevelopment of fast-neutron sodium-cooled Generation IV reactors is resulting ...
In the framework of the development of new nuclear plants, we have studied the feasibility of produc...
International audienceFor new fast-neutron sodium-cooled GEN IV reactors, the candidate cladding mat...
International audienceThe oxide dispersion strengthened (ODS) ferritic and martensitic steels are ca...
In this paper, an elastic plastic behaviour model based on internal state variables is investigated....
International audienceFor new fast-neutron sodium-cooled Generation IV nuclear reactors, the candida...
The optimization of the forming of ODS tubes is linked to the choice of an appropriated constitutive...
Co-encadrement de la thèse : Katia MOCELLINFor new fast-neutron sodium-cooled Generation IV reactors...
International audienceFerritic Oxide Dispersion Strengthened (ODS) steels are investigated as potent...
AbstractIn this paper, an elastic plastic behaviour model based on internal state variables is inves...
International audienceOxides Dispersed strengthened (ODS) stainless steels are foreseen for fuel cla...
Oxide Dispersion Strengthened ferritic/martensitic alloys are developed as prospective cladding mate...
International audienceOxide dispersion strengthened (ODS) steels are suitable candidates for claddin...
International audienceDevelopment of fast-neutron sodium-cooled Generation IV reactors is resulting ...
In the framework of the development of new nuclear plants, we have studied the feasibility of produc...
International audienceFor new fast-neutron sodium-cooled GEN IV reactors, the candidate cladding mat...
International audienceThe oxide dispersion strengthened (ODS) ferritic and martensitic steels are ca...
In this paper, an elastic plastic behaviour model based on internal state variables is investigated....
International audienceFor new fast-neutron sodium-cooled Generation IV nuclear reactors, the candida...
The optimization of the forming of ODS tubes is linked to the choice of an appropriated constitutive...
Co-encadrement de la thèse : Katia MOCELLINFor new fast-neutron sodium-cooled Generation IV reactors...
International audienceFerritic Oxide Dispersion Strengthened (ODS) steels are investigated as potent...
AbstractIn this paper, an elastic plastic behaviour model based on internal state variables is inves...
International audienceOxides Dispersed strengthened (ODS) stainless steels are foreseen for fuel cla...
Oxide Dispersion Strengthened ferritic/martensitic alloys are developed as prospective cladding mate...
International audienceOxide dispersion strengthened (ODS) steels are suitable candidates for claddin...