Charpy impact tests on martensitic/ferritic steels after irradiation in SINQ Target-3
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The radiation resistance of two promising ferritic ODS steels, PM2000 and 15CRA-3, is studied. More specifically, the effect of helium on these materials is studied by examining the swelling and hardening after He+ implantation to ∼1 dpa at 4000 appm/dpa. ...
Helium atoms are known to have a significant impact on materials used in fission and fusion reactors. In particular, the presence of helium atoms can change the mechanical properties and degrade the lifetime of reactors. In order to develop the helium-resi ...
In the quest of the structural materials for the future fusion reactor, it has been shown that ferritic/martensitic (F/M) steels are very promising candidates, with a good radiation resistance in terms of damage accumulation in the microstructure relative ...
The best-known property of superfluid helium is the vanishing viscosity that objects experience while moving through the liquid with speeds below the so-called critical Landau velocity. This critical velocity is generally considered a macroscopic property ...
In the present work, LBE (lead-bismuth eutectic) embrittlement effects on ferritic/martensitic (FM) steels have been studied by conducting slow-strain-rate tensile (SSRT) testing on T91 and F82H steels either in Ar or in liquid LBE after irradiation to dos ...
Ferritic/martensitic (FM) steels, F82H and Optimax-A, were irradiated up to 11.3 dpa/1175 appm He in Target-3 of the Swiss Spallation Neutron Source (SINQ). To investigate helium-induced hardening effect, micro-hardness and microstructure of the irradiated ...
The clustering of helium in bcc (body centered cubic) iron and the growth of a helium bubble are simulated at the atomistic level for the helium-rich vacancy-poor condition. It is shown that a 1/2 < 111 > dislocation loop is formed as a sequential collecti ...
The irradiation hardening of the Eurofer97 steel following 590 MeV proton irradiations was determined at three different irradiation temperatures, 50 °C, 250 °C and 350 °C, and various doses up to about 1.3 displacement per atom. The dose and temperature d ...
In this work we have studied brittle fracture in high-chromium reduced activation tempered martensitic steels foreseen as structural materials for thermonuclear fusion reactors. Developing the adequate materials that can withstand the severe irradiation co ...
