Results 291 to 300 of about 1,249,952 (349)
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Irradiation hardening behavior of polycrystalline metals after low temperature irradiation
Journal of Nuclear Materials, 2004Abstract Irradiation hardening behaviors of body-centered cubic (bcc), face-centered cubic (fcc), and hexagonal close-packed (hcp) alloys and pure metals were characterized after neutron, or proton and neutron irradiations at low temperatures (⩽200 °C).
T.S Byun, K Farrell
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Irradiation hardening of reduced activation martensitic steels
Journal of Nuclear Materials, 1996Abstract Irradiation response on the tensile properties of 9Cr2W steels has been investigated following FFTF/MOTA irradiations at temperatures between 646 and 873 K up to doses between 10 and 59 dpa. The largest irradiation hardening accompanied by the largest decrease in the elongation is observed for the specimens irradiated at 646 K at doses ...
A. Kimura +3 more
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Electron irradiation hardening in niobium single crystals
Journal of Nuclear Materials, 1981Abstract Electron irradiation hardening was investigated in niobium single crystals with a tensile axis in the middle of the standard triangle. Specimens were irradiated at 15 K with 2 MeV electrons and deformed at 10 K in tension. The yield stress increased proportionally with the square-root of the dosage.
J. Nagakawa, M. Meshii
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Journal of Nuclear Materials, 2019
Copper and phosphorus as impurities and nickel as alloying element were already a long time ago identified to significantly affect radiation embrittlement of reactor pressure vessel materials.
R. Chaouadi +3 more
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Copper and phosphorus as impurities and nickel as alloying element were already a long time ago identified to significantly affect radiation embrittlement of reactor pressure vessel materials.
R. Chaouadi +3 more
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Numerical simulation of irradiation hardening in Zirconium
Journal of Nuclear Materials, 2013Abstract A phase field model is developed to simulate interactions between gliding dislocations and irradiation induced damage loops (i.e., vacancy and self-interstitial loops) in Zirconium. Pinning contact interactions and long-range elastic interactions are simulated, with populations of defects generated based on experimental observations of ...
A. Boyne +3 more
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, 2021
In this work, we have performed neutron irradiation and sub-sequent microstructural and micro-hardness measurements on a series of tungsten grades. The neutron irradiation was performed in BR2 reactor up to 0.2 dpa at 600, 800 and 1200 °C.
A. Dubinko +10 more
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In this work, we have performed neutron irradiation and sub-sequent microstructural and micro-hardness measurements on a series of tungsten grades. The neutron irradiation was performed in BR2 reactor up to 0.2 dpa at 600, 800 and 1200 °C.
A. Dubinko +10 more
semanticscholar +1 more source
Effect of niobium content on irradiation microstructure and hardening in FeCrAl-based alloys
, 2021Iron-chromium-aluminum (FeCrAl) alloys with different content of niobium (Nb)—0, 0.4 wt%, 0.8 wt%, and 1.2 wt%—were designed and prepared. All samples were then irradiated with 2.4 MeV Fe2+ ion to the dose of 1 and 15 displacements per atom (dpa) at 400 °
Xiong Zhou +9 more
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Assessment of irradiation hardening by DD simulations
Computational Materials Science, 2014Abstract Understanding of material degradation due to irradiation in structural materials of future reactors is of prime importance for current research as these materials are expected to operate at severe conditions of high temperature and high irradiation doses. The hierarchical multi-scale simulations act as supplement to the costly experiments on
P.V. Durgaprasad, B.K. Dutta, R.K. Singh
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Journal of Nuclear Materials, 2018
9Cr ferritic/martensitic steels are promising materials for in-core components in advanced Gen-IV reactors. In these applications, their long-term microstructural stability under thermal exposure and resistance to neutron irradiation are essential ...
Dandan Zhao +4 more
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9Cr ferritic/martensitic steels are promising materials for in-core components in advanced Gen-IV reactors. In these applications, their long-term microstructural stability under thermal exposure and resistance to neutron irradiation are essential ...
Dandan Zhao +4 more
semanticscholar +1 more source
The hardening of copper by neutron irradiation
Philosophical Magazine, 1959Copper wires of 0.060 in. diameter were irradiated at 50 deg C for 1 to 3 weeks. At a fixed neutron dose and testing temperature the yield stress of irradiated polycrystalline copper increases within accuracy limits of experimental measurements. Lattice friction hardening and source hardening proceed simultaneously.
M. A. Adams, P. R. B. Higgins
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