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EFFECT OF PROGRESSIVE AGING TREATMENT ON THE PROPERTIES AND MICROSTRUCTURE OF THE HIGH-HARD ELASTIC NICKEL-CHROMIUM-ALUMINIUM ALLOY
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《Acta Metallurgica Sinica(English Letters)》 SCIE EI CAS CSCD 1995年第1期47-51,共5页
A dispersion-hardened high-hard elastic alloy is developed by adding 3%/ of aluminium (Al) to the nickel-chromium alloy. The experimental results show that after a progressive aging of the alloy at 550℃ or 5 h, sup... A dispersion-hardened high-hard elastic alloy is developed by adding 3%/ of aluminium (Al) to the nickel-chromium alloy. The experimental results show that after a progressive aging of the alloy at 550℃ or 5 h, supersaturated Cr(α)-rich phase (80 wt% Cr)formed. The Cr content of this phase is by 40 wt% higher than that in as-prepared alloy. An analysis of quantitative metallography shows that the seperated Cr(α)-rich phase grains have an average size(D) of 1.8225 mm and the total area of the particles is 16. 7% of the measured area (Pa = 16.7%). The large amount of dispersively distributed supersaturated Cr(α)-rich phase which are seperated out during progressive aging process strengthen the alloy matrix, and raise the hardness and bending strength of the alloy. 展开更多
关键词 dispersion hardening aging treatment supersaturated Cr (α)-rich phase
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Atomic-scale mechanisms of void strengthening in tungsten 被引量:1
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作者 Yuri N.Osetsky 《Tungsten》 2021年第1期65-71,共7页
Neutron and heavy-ion irradiation of tungsten produces nanometer-size vacancy voids,gas-filled bubbles and dislocation loops.These defect features can a ect mechanical properties and the impact can be quite significan... Neutron and heavy-ion irradiation of tungsten produces nanometer-size vacancy voids,gas-filled bubbles and dislocation loops.These defect features can a ect mechanical properties and the impact can be quite significant because of their high density.Understanding the basic mechanisms of mechanical properties degradation is necessary for predicting radiation e ects.Predictions can be made using discrete dislocation dynamics or/and finite element approaches which,however,need local interaction mechanisms as inputs.Such knowledge can be provided only by atomic-scale modeling.This paper reports the results of an extensive atomic-scale modeling study of the interactions between moving edge dislocations and voids in tungsten.The main focus is on the e ects of the void size and ambient temperature.Critical resolved shear stress was calculated for voids up to 9 nm in diameter.Atomistic results are compared with the theoretical approach and with those obtained earlier for voids in body centered cubic(bcc)iron.An important role of the void surface has been revealed. 展开更多
关键词 TUNGSTEN Neutron irradiation Voids Radiation-induced hardening Dislocations Dispersed barrier hardening
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