Results 41 to 50 of about 5,894 (297)
The effect of post-irradiation annealing on the microstructures and mechanical properties of V-4Cr-4Ti alloys was studied. Helium-hydrogen-irradiated sequentially V-4Cr-4Ti alloys at room temperature (RT) were undergone post-irradiation annealing at 450 °
Shaoning Jiang, Zhiming Wang
doaj +1 more source
Neutron irradiation hardening and microstructure changes in Fe–Mn binary alloys [PDF]
Irradiation hardening and microstructure changes in Fe–Mn binary alloys were investigated after neutron irradiation at 290 °C and up to 0.13 dpa. Significant irradiation hardening comparable to that of Fe–1 at.%Cu alloy was observed in Fe–1 at.%Mn alloy.
Masashi Saito +7 more
core +1 more source
Atom probe examinations of Zircaloy irradiated at nominally 358 °C
Zircaloy-2 and Zircaloy-4 were neutron irradiated at 358 °C in the high flux isotope reactor (HFIR) to a neutron fluence of 29.6 × 1024 n/m2 (E > 1 MeV) and the resultant irradiation hardening was measured by tensile testing.
B.V. Cockeram +4 more
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Indentation testing on 3 MeV proton irradiated tungsten
Tungsten samples have been irradiated with 3 MeV protons with dose rates of 1×10-04 to 5×10-05 dpa/s to doses of 0.01–0.67 dpa at 360 K in a pilot experiment. Micro- and macro-indentation were used to measure irradiation hardening in the samples.
R. Rayaprolu +5 more
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Irradiation hardening and ductility loss of Eurofer97 steel variants after neutron irradiation to ITER-TBM relevant conditions [PDF]
Ten Eurofer97 steel variants, produced by non-standard fabrication-processing routes and modified alloying chemistries, were studied by neutron irradiations in the high flux isotope reactor. The irradiations were performed to ITER-TBM relevant conditions
Rieth M. +12 more
core +1 more source
Damage characteristics of selective laser melted 304L stainless steel under Xe ion irradiation
BackgroundOwing to its excellent mechanical properties and corrosion resistance, 304L stainless steel is widely used as the core structure material in advanced nuclear power systems.PurposeThis study aims to investigate the damage characteristics of ...
LI Ying +6 more
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An amount of 100 dpa Si2+ irradiation was used to study the effect of transmutation rhenium content on irradiated microscopic defects and hardening in W-xRe (x = 0, 1, 3, 5 and 10 wt.%) alloys at 550 °C.
Fengfeng Luo +6 more
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Analysis of Radiation Hardening Effect of Ferritic Martensitic Steel Based on Bayesian Optimization
Ferritic/martensitic (F/M) steel is a candidate material for key structures in fourth-generation nuclear energy systems (such as fusion reactors and fast reactors).
Yue He +5 more
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Evaluation of Irradiation Hardening of Fe-Ion Irradiated F82H by Nano-Indentation Techniques [PDF]
The effects of small amount (1 or 2 wt.%) of Ni additionson the irradiation hardening of the reduced-activation ferritic/martensitic steel, F82H, used as fusion reactor blanket structural materials were investigated by means of Fe-ion irradiation ...
Akihiko Kimura +6 more
core +1 more source
Effect of Au-ions irradiation on microstructure and mechanical properties of FeCrAl coating
Six kinds of FeCrAl coatings with different Cr and Al contents were irradiated by 6 MeV Au-ions with a damage level of 20 dpa. The results showed that the surface roughness and grain size of the coatings increased significantly after irradiation ...
Wei Zhang +7 more
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