Reduced activation ferritic/martensitic steels (RAFM) represented by binary Fe-Cr alloys, with different chromium content, were studied in as-received state as well as after helium ions implantation. In order to study changes in dependence on the temperature, thermal annealing of He ions implanted Fe-11.62%Cr specimens was performed. Measurements by Pulsed Low Energy Positron System (PLEPS) in Garching, Germany were performed afterwards. Annealing out of defects at lower temperatures was not significant as was expected and some uncertainties are present. Extensive decrease of positron lifetime of defects was observed in specimens annealed at temperature 600 ºC.JRC.F.4-Nuclear Reactor Integrity Assessment and Knowledge Managemen
The degradation of reactor pressure vessel steels under irradiation, which results from the hardenin...
Ferritic-martensitic (F-M) steels are considered as lead candidate structural materials for Generati...
The first walls of future fusion reactors will be exposed to 14 MeV neutron irradiation. In order to...
AbstractReduced activation ferritic/martensitic steels (RAFM) represented by binary Fe-Cr alloys, wi...
Binary Fe-11.62wt%Cr alloys were investigated in as-received state as well as after a two step heliu...
Chromium is an element with significant effect on the elevated temperature corrosion resistance and ...
The paper discusses our recent experiments focused on the chromium influence on the microstructural ...
Reduced activation high-chromium ferritic/martensitic steels are candidate materials for Generation ...
Reduced Activation Ferritic/Martensitic steels are being extensively studied because of their forese...
Positron annihilation, microstructural and hardness studies were carried out in a 9Cr reduced activa...
High chromium steels belong to the most prospective materials for reactor pressure vessel of High Te...
Reduced Activation Ferritic/Martensitic steels are being extensively studied because of their forese...
Iron-chromium alloys are used as a model to study the microstructural evolution of defects in irradi...
This paper is focused on four different commercial oxide-dispersion-strengthened ferritic steels (MA...
Oxide dispersion strengthened steels are candidate materials for nuclear reactor applications due to...
The degradation of reactor pressure vessel steels under irradiation, which results from the hardenin...
Ferritic-martensitic (F-M) steels are considered as lead candidate structural materials for Generati...
The first walls of future fusion reactors will be exposed to 14 MeV neutron irradiation. In order to...
AbstractReduced activation ferritic/martensitic steels (RAFM) represented by binary Fe-Cr alloys, wi...
Binary Fe-11.62wt%Cr alloys were investigated in as-received state as well as after a two step heliu...
Chromium is an element with significant effect on the elevated temperature corrosion resistance and ...
The paper discusses our recent experiments focused on the chromium influence on the microstructural ...
Reduced activation high-chromium ferritic/martensitic steels are candidate materials for Generation ...
Reduced Activation Ferritic/Martensitic steels are being extensively studied because of their forese...
Positron annihilation, microstructural and hardness studies were carried out in a 9Cr reduced activa...
High chromium steels belong to the most prospective materials for reactor pressure vessel of High Te...
Reduced Activation Ferritic/Martensitic steels are being extensively studied because of their forese...
Iron-chromium alloys are used as a model to study the microstructural evolution of defects in irradi...
This paper is focused on four different commercial oxide-dispersion-strengthened ferritic steels (MA...
Oxide dispersion strengthened steels are candidate materials for nuclear reactor applications due to...
The degradation of reactor pressure vessel steels under irradiation, which results from the hardenin...
Ferritic-martensitic (F-M) steels are considered as lead candidate structural materials for Generati...
The first walls of future fusion reactors will be exposed to 14 MeV neutron irradiation. In order to...