Radiation hardening and embrittlement of A533B steels are controlled by formation of dislocation loop density.. To investigate the microstructural evolution of these materials, A533B steels and several Fe model alloys containing Mn, Si and Ni were irradiated by HVEM in the temperature range of room temp. to 673K. In all temperature range, formation of interstitial type dislocation loops as enhanced by Mn additions. From the temperature dependence of loop density, binding energy between Fe and Mn, is estimated as 0.22 eV
Hydrogen can be induced in various ways into reduced-activation ferritic/martensitic (RAFM) steels w...
The understanding of microstructural defects behavior after neutron irradiation is crucial for asses...
A review of the microstructure of irradiated reduced activation ferritic/martensitic steels is prese...
The microstructure evolution of nuclear reactor pressure vessel A508-3 steel irradiated by heavy ion...
It is well known that radiation hardening and embrittlement of A533B steels are very sensitive to Cu...
International audienceThe evolution of radiation damage in steels is a major issue for the safe oper...
Fe-Cr ferritic/martensitic (F/M) steels have been proposed as one of the candidate materials for the...
Microstructural and hardening changes of Fe-0.2wt.%V alloy and pure Fe irradiated with 100 keV hydro...
International audienceA correlation is attempted between microstructural observations by various com...
In an effort to better understand the nature of irradiation embrittlement of low alloy steels, in-si...
International audienceTemperature effect on dislocation loop density and radiation-induced segregati...
Ferritic/martensitic steels are candidate materials for structural and cladding components d...
To investigate the influence of heat load on microstructure change, we conducted in-situ experiments...
Hydrogen can be induced in various ways into reduced-activation ferritic/martensitic (RAFM) steels w...
The understanding of microstructural defects behavior after neutron irradiation is crucial for asses...
A review of the microstructure of irradiated reduced activation ferritic/martensitic steels is prese...
The microstructure evolution of nuclear reactor pressure vessel A508-3 steel irradiated by heavy ion...
It is well known that radiation hardening and embrittlement of A533B steels are very sensitive to Cu...
International audienceThe evolution of radiation damage in steels is a major issue for the safe oper...
Fe-Cr ferritic/martensitic (F/M) steels have been proposed as one of the candidate materials for the...
Microstructural and hardening changes of Fe-0.2wt.%V alloy and pure Fe irradiated with 100 keV hydro...
International audienceA correlation is attempted between microstructural observations by various com...
In an effort to better understand the nature of irradiation embrittlement of low alloy steels, in-si...
International audienceTemperature effect on dislocation loop density and radiation-induced segregati...
Ferritic/martensitic steels are candidate materials for structural and cladding components d...
To investigate the influence of heat load on microstructure change, we conducted in-situ experiments...
Hydrogen can be induced in various ways into reduced-activation ferritic/martensitic (RAFM) steels w...
The understanding of microstructural defects behavior after neutron irradiation is crucial for asses...
A review of the microstructure of irradiated reduced activation ferritic/martensitic steels is prese...