Results 21 to 30 of about 23,999 (306)
Nuclear Materials and Energy, 2021 Oxide dispersion strengthened (ODS) Cu alloys are expected to have high strength and superior irradiation resistance that are necessary characteristics for the divertor components of fusion reactors.
Yuchen Liu +4 more
doaj +1 more source
Nanoscale Research Letters, 2018 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
A Grid of Relativistic, non-LTE Accretion Disk Models for Spectral Fitting of Black Hole Binaries [PDF]
, 2006 Self-consistent vertical structure models together with non-LTE radiative transfer should produce spectra from accretion disks around black holes which differ from multitemperature blackbodies at levels which may be observed. High resolution, high signal-
Ivan Hubeny +3 more
core +1 more source
Effect of self-ion irradiation on hardening and microstructure of tungsten
Nuclear Materials and Energy, 2016 The irradiation hardening and microstructures of pure W and W–3%Re for up to 5.0 dpa by self-ion irradiation were investigated in this work. The ion irradiation was conducted using 18 MeV W6+ at 500 and 800°C.
T. Hwang +7 more
doaj +1 more source
Ion Irradiation Defects and Hardening in FeCrAl Alloy
Metals, 2022 The self-ion irradiation experiments of FeCrAl and Y−FeCrAl alloys are carried out at 330 °C to 1–10 displacements per atom (dpa). The formation of dislocation loops in these alloys is investigated by transmission electron microscopy (TEM) and nano ...
Fang Li +8 more
doaj +1 more source
Design of Radiation-Hardened Rare-Earth Doped Amplifiers Through a Coupled Experiment/Simulation Approach [PDF]
, 2013 We present an approach coupling a limited experimental number of tests with numerical simulations regarding the design of radiation-hardened (RH) rare earth (RE)-doped fiber amplifiers.
Boscaino, Roberto +15 more
core +4 more sources
Atom probe examinations of Zircaloy irradiated at nominally 358 °C
Nuclear Materials and Energy, 2019 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
doaj +1 more source
Indentation testing on 3 MeV proton irradiated tungsten
Nuclear Materials and Energy, 2020 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
doaj +1 more source
Nanomaterials, 2023 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
doaj +1 more source
MetalsRadiation hardening is studied for stainless austenitic and ferritic-martensitic chromium steels after ion and neutron irradiation at various temperatures. Austenitic and ferritic-martensitic steels irradiated up to 30 dpa in various nuclear reactors and
Boris Margolin +2 more
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