Results 81 to 90 of about 5,873 (297)

Effects of helium production, displacement damage on mechanical properties and surface acoustic wave in austenitic stainless steels and martensitic steel

open access: yesNuclear Materials and Energy, 2018
The effects of helium production, displacement damage on mechanical properties and microstructures were investigated in some specimens such as austenitic stainless steels of SUS304 and SUS316 and a high chromium martensitic steel of HCM12A steels ...
E. Wakai   +8 more
doaj   +1 more source

Discrete Dislocation Dynamics Simulations of Irradiation Hardening in Nuclear Materials [PDF]

open access: yes, 2020
Neutron irradiation can severely impact the mechanical behavior of nuclear structural materials. Irradiation introduces a high density of nanometric defects that block dislocation motion and result in hardening and a loss of ductility often associated ...
Po, Giacomo   +5 more
core   +1 more source

Thermodynamic Pathways of Nonequilibrium Solidification in Wire‐Arc Additive Manufacturing Fe‐Based Multicomponent Alloy Structures

open access: yesAdvanced Engineering Materials, EarlyView.
Geometry‐driven thermal behavior in wire‐arc additive manufacturing (WAAM) influences microstructural evolution during nonequilibrium solidification of a chemically complex Fe–Cr–Nb–W–Mo–C nanocomposite system. By comparing different deposits configurations, distinct entropy–cooling rate correlations, segregation, and carbide evolution are revealed ...
Blanca Palacios   +5 more
wiley   +1 more source

Pyramidal Structures on Yttria‐Stabilized Zirconia after High Temperature Exposure at 1500°C: New Features on an Old Material

open access: yesAdvanced Engineering Materials, EarlyView.
New features on yttria‐stabilized zirconia after exposure at 1500°C: Newly discovered pyramidal structures on an old material. After exposure at 1550°C on the cross section of YSZ new features, namely pyramidal structures are discovered. These structures grow with time, increase in numbers, appear as singularities, are often arranged in strings, and ...
Doris Sebold   +2 more
wiley   +1 more source

Microstructural changes in He-irradiated V-Cr-Ti alloys with low Ti addition at 700 °C

open access: yesNuclear Materials and Energy
V-Cr-Ti alloys with reduced Ti contents are expected to be good candidates as recyclable structural materials for fusion reactors. Herein, He irradiation was applied to V-4Cr-xTi (x = 0 to 4) alloys to investigate the additional effect of Ti and gas ...
Yichen Zou   +3 more
doaj   +1 more source

Copper precipitate hardening of irradiated RPV materials and implications on the superposition law and re-irradiation kinetics [PDF]

open access: yes, 2005
Copper is known to play an important role in irradiation hardening and embrittlement of RPV materials. This is particularly true for old vessels. Indeed, while the Cu-content is low (< 0.1%) in modern RPV materials, it often exceeded 0.15% in older ...
Chaouadi, R., Gerard, Raphaël
core   +1 more source

Field Report from Collaborative Research Center 1625: Heterogeneous Research Data Management Using Ontology Representations

open access: yesAdvanced Engineering Materials, EarlyView.
A unified research data management framework for heterogeneous materials data is presented. The system integrates multimodal datasets using ontologies and knowledge graphs, enabling interoperability and FAIR (findable, accessible, interoperable, reusable) data principles. By linking data across scales and workflows, it supports reproducible, Artifitial
Doaa Mohamed   +6 more
wiley   +1 more source

Microstructure-Informed Prediction of Hardening in Ion-Irradiated Reactor Pressure Vessel Steels

open access: yesMetals
Ion irradiation combined with nanoindentation is a promising tool for studying irradiation-induced hardening of nuclear materials, including reactor pressure vessel (RPV) steels.
Libang Lai   +8 more
doaj   +1 more source

Controlled irradiation hardening of tungsten by cyclic recrystallization [PDF]

open access: yes, 2019
The economical lifetime of the divertor is a key concern for realizing nuclear fusion reactors that may solve the world's energy problem. A main risk is thermo-mechanical failure of the plasma-facing tungsten monoblocks, as a consequence of irradiation ...
Geers, MGD Marc   +5 more
core   +1 more source

Towards Defect Phase Diagrams: From Research Data Management to Automated Workflows

open access: yesAdvanced Engineering Materials, EarlyView.
A research data management infrastructure is presented for the systematic integration of heterogeneous experimental and simulation data required for defect phase diagrams. The approach combines openBIS with a companion application for large‐object storage, automated metadata extraction, provenance tracking and federated data access, thereby supporting ...
Khalil Rejiba   +5 more
wiley   +1 more source

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