Reduced activation martensitic stainless steel EUROFER97 was homogeneously implanted at 250 degrees C with 0.25 at.% helium, and was subsequently annealed in vacuum for 10 h at 550 degrees C and 750 degrees C, respectively. Tensile testing at room temperature and at 250 degrees C showed increase in strength and decrease of ductility by the implantation. Both changes recovered during annealing: While the strength was reduced by annealing to values between unimplanted and implanted condition, ductility was increased even beyond that of virgin material. This means, the implanted plus annealed material showed improved behaviour even when compared to the virgin material: higher strength and greater ductility. Including the results on fracture su...
The production of helium bubbles in advanced gas-cooled reactor (AGR) cladding could represent a sig...
An advanced oxide dispersion strengthened (ODS) ferritic steel with very fine oxide particles has be...
High temperature helium embrittlement, swelling and irradiation creep are the main technical problem...
Low activation 9%Cr martensitic steels EUROFER97, pure tantalum, and low carbon austenitic stainless...
Tensile tests and microstructural examinations were performed on 100 gm thick specimens of 9Cr-1Mo (...
The effect of post-helium irradiation annealing on bubbles and nanoindentation hardness of two reduc...
Tensile tests and microstructural examinations were performed on 100 $\mu$m thick specimens of 9Cr-1...
Experiments with low helium concentrations suggest that ferritic-martensitic steels are more resista...
About 380 mum thick specimens of low-activation martensitic stainless steel EUROFER97 were homogeneo...
An experimental characterization was conducted of helium effects on the mechanical properties of a 9...
Martensitic stainless steels are candidate materials for the target structure of the European Spalla...
Irradiation is known to lead to degradation of mechanical properties of materials. Structural materi...
The effects of helium (He) on mechanical properties of hot-rolled pure W were investigated using a h...
Low temperature irradiation embrittlement is one of the major criteria to determine the lifetime of ...
Reduced Activation Ferritic/Martensitic steels are being extensively studied because of their forese...
The production of helium bubbles in advanced gas-cooled reactor (AGR) cladding could represent a sig...
An advanced oxide dispersion strengthened (ODS) ferritic steel with very fine oxide particles has be...
High temperature helium embrittlement, swelling and irradiation creep are the main technical problem...
Low activation 9%Cr martensitic steels EUROFER97, pure tantalum, and low carbon austenitic stainless...
Tensile tests and microstructural examinations were performed on 100 gm thick specimens of 9Cr-1Mo (...
The effect of post-helium irradiation annealing on bubbles and nanoindentation hardness of two reduc...
Tensile tests and microstructural examinations were performed on 100 $\mu$m thick specimens of 9Cr-1...
Experiments with low helium concentrations suggest that ferritic-martensitic steels are more resista...
About 380 mum thick specimens of low-activation martensitic stainless steel EUROFER97 were homogeneo...
An experimental characterization was conducted of helium effects on the mechanical properties of a 9...
Martensitic stainless steels are candidate materials for the target structure of the European Spalla...
Irradiation is known to lead to degradation of mechanical properties of materials. Structural materi...
The effects of helium (He) on mechanical properties of hot-rolled pure W were investigated using a h...
Low temperature irradiation embrittlement is one of the major criteria to determine the lifetime of ...
Reduced Activation Ferritic/Martensitic steels are being extensively studied because of their forese...
The production of helium bubbles in advanced gas-cooled reactor (AGR) cladding could represent a sig...
An advanced oxide dispersion strengthened (ODS) ferritic steel with very fine oxide particles has be...
High temperature helium embrittlement, swelling and irradiation creep are the main technical problem...