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Irradiation hardening behavior of polycrystalline metals after low temperature irradiation

Journal of Nuclear Materials, 2004
Abstract 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
openaire   +1 more source

Irradiation hardening of reduced activation martensitic steels

Journal of Nuclear Materials, 1996
Abstract Irradiation response on the tensile properties of 9Cr2W 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, 1981
Abstract 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
openaire   +1 more source

Neutron irradiation hardening of chemically-tailored RPV steels with respect to Cu/P and Ni/Mn elements

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
semanticscholar   +1 more source

Numerical simulation of irradiation hardening in Zirconium

Journal of Nuclear Materials, 2013
Abstract 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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Microstructure and hardening induced by neutron irradiation in single crystal, ITER specification and cold rolled tungsten

, 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
semanticscholar   +1 more source

Effect of niobium content on irradiation microstructure and hardening in FeCrAl-based alloys

, 2021
Iron-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
semanticscholar   +1 more source

Assessment of irradiation hardening by DD simulations

Computational Materials Science, 2014
Abstract 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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Investigation of ion irradiation hardening behaviors of tempered and long-term thermal aged T92 steel

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
semanticscholar   +1 more source

The hardening of copper by neutron irradiation

Philosophical Magazine, 1959
Copper 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
openaire   +1 more source

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