Results 11 to 20 of about 690,599 (300)
Metals, 2022 Tungsten (W) is considered to be the most promising plasma-facing material in fusion reactors. During their service, severe irradiation conditions create plenty of point defects in W, which can significantly degrade their performance.
Linyu Li +8 more
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Dislocation loop and irradiation-induced synergistic-competitive mechanism in Cu-rich precipitates: a phase-field study [PDF]
Scientific ReportsBoth irradiation and dislocations have been proposed as routes to rationally manipulate spatial distribution and micromorphology of precipitate. An interesting effect emerges in Fe–10at.%Cu–3at.%Mn–1.5at.%Ni–1.5at.%Al alloy due to the synergistic ...
Wenkui Yang +5 more
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Communications Materials, 2023 Dislocation loops are ubiquitous in irradiated materials, and dislocation loop bias plays a critical role in void swelling. However, due to complicated interactions between dislocation loops and point defects, it is challenging to evaluate the bias ...
Ziang Yu, Haixuan Xu
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Behavior of a self-interstitial-atom type dislocation loop in the periphery of an edge dislocation in BCC-Fe [PDF]
Nuclear Materials and Energy, 2016 The behavior of the dislocation loop of a self-interstitial atom (SIA) near an edge dislocation and its conservative climb process were modeled in body-centered cubic Fe by incorporating loop rotation.
Sho Hayakawa +5 more
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Investigation of Interaction between Dislocation Loop and Coherent Twin Boundary in BCC Ta Film during Nanoindentation [PDF]
Nanomaterials, 2017 In this work, the interaction between dislocation loop (DL) and coherent twin boundary (CTB) in a body-centered cubic (BCC) tantalum (Ta) film during nanoindentation was investigated with molecular dynamics (MD) simulation.
Cheng Huang +5 more
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Yuanzineng kexue jishu, 2023 After neutron irradiation, RAFM steel will produce two types of interstitial dislocation loops (1/2〈111〉 loop and 〈100〉 loop), resulting in radiation hardening and embrittlement after long service.
XU Xincheng;NIE Ningming;WANG Jin;HE Xinfu;ZENG Yan;ZHANG Jilin;WANG Jue;WAN Jian
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Review and critical assessment of dislocation loop analyses on EUROFER 97 [PDF]
Nuclear Materials and Energy, 2018 The understanding of microstructural defects behavior after neutron irradiation is crucial for assessing the applicability of reduced activation ferritic/martensitic (RAFM) steel EUROFER 97 in future fusion reactors.
C. Dethloff, E. Gaganidze, J. Aktaa
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Nuclear Analysis, 2022 Fe13.5Cr4.7Al alloy was irradiated in-situ with 400 keV Fe+ in TEM at RT and 748 K. The evolution of dislocation loops under the influence of temperatures, irradiation dose, dislocation lines and precipitates were characterized in detail.
Kefei Pei +6 more
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Materials Research Express, 2023 The interaction of hydrogen and helium atoms with 1/2 〈111〉 interstitial dislocation loop in tungsten is investigated by molecular dynamics simulation. The binding energies of hydrogen and helium atoms around dislocation loop are calculated by molecular ...
Bai-Chuan Xu +7 more
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LACBED characterization of dislocation loops [PDF]
Philosophical Magazine, 2006 The characterization of the amplitude and sign of the Burgers vector of perfect or partial dislocations from large-angle convergent-beam electron diffraction (LACBED) patterns is now a routine technique following the original idea proposed by Cherns and Preston [Proceedings of ICEM-11, Kyoto, Japan, pp. 721–722 (1986)].
Morniroli, Jean-Paul +3 more
openaire +2 more sources