Helium-induced hardening effect in ferritic/martensitic steels F82H and Optimax-A irradiated in a mixed spectrum of high energy protons and spallation neutrons
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Charpy impact tests were performed on martensitic/ferritic (MF) steels T91, F82H, Optifer-V and Optimax-A/-C irradiated in SINQ Target-3 up to 7.5 dpa and 500 appm He in a temperature range of 120-195 degrees C. Results demonstrate that for all the four ki ...
Ferritic/martensitic steels considered as candidate first-wall materials for fusion reactors experience significant radiation hardening at temperatures below similar to400 degreesC. A number of experimental studies in ferritic alloys, performed at 1/2(111) ...
The asphalt rubber blends design is an empirical procedure and is quite sensitive to the variability of the components properties. A better understanding of the physical phenomenon involved during the curing process is a prerequisite step to propose a rati ...
This work is focussed on a high carbon tool steel used for the production of files. The mechanical properties of the files depend on a hardening thermal treatment that produces a martensitic structure. Thus, the motivation for this work is technological: w ...
The effects of neutron irradiation on austenitic stainless steels, usually used for the manufacturing of internal elements of nuclear reactors (e.g. the core shrouds), are the alteration of the microchemistry and the microstructure, and, as a consequence, ...
Modeling of the constitutive behavior was undertaken for Fe- Cr-C tempered martensitic alloys. Tensile tests were carried out at room temperature and constant nominal strain rate. In order to obtain a fully martensitic structure with different prior austen ...
Nuclear materials have been successfully employed in commercial fission reactors for many decades. Research and material development for advanced fission system and future thermo-nuclear fusion reactors have acquired maturity while great challenges remain ...
Reduced activation ferritic/martensitic (RAFM) steels are the reference structural materials for future fusion reactors. They have proven to be a good alternative to austenitic steels for their higher swelling resistance, lower damage accumulation and impr ...
Neutron-irradiation-induced embrittlement of a 2.25Cr1Mo steel is investigated by means of small punch testing along with scanning electron trucroscopy. There is an apparent irradiation-induced embrittlement effect after the steel is irradiated at about 40 ...
The procedures followed to produce Y2O3-dispersed EUROFER 97 powder ready to be compacted and hot isostatic pressing processed are reported. An attrition mill has been used under controlled conditions. The compositional and microstructural characterization ...
