Results 91 to 100 of about 5,894 (297)

Effects of deuterium plasma exposure and helium ions irradiation on nanoindentation hardness of tungsten

open access: yesNuclear Materials and Energy
Irradiation hardening is one of the service performance concerns for tungsten in fusion reactors. This work investigated the effect of deuterium (D) plasma exposure and helium (He) ions irradiation on the hardening behavior of the same tungsten sample ...
Hong Zhang   +4 more
doaj   +1 more source

Microstructural Evolution and Vacancy Defect Formation in Mn–Mo–Ni RPV Steel Under Low Cycle Fatigue: Insights From EBSD and PALS

open access: yesAdvanced Engineering Materials, EarlyView.
Low‐cycle fatigue damage in Mn–Mo–Ni reactor pressure vessel steel is examined using a combined electron backscatter diffraction and positron annihilation lifetime spectroscopy approach. The study correlates texture evolution, dislocation substructure development, and vacancy‐type defect formation across uniform, necked, and fracture regions, providing
Apu Sarkar   +2 more
wiley   +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

About Relation Between Irradiation Hardening of Ferritic Steels and Ductile Fracture Toughness Decrease [PDF]

open access: yes, 2009
We showed recently that temperature dependence of the ductile fracture toughness can be predicted on the base of two assumptions: 1) assumption of constant characteristic length, 2) assumption of proportionality between J-R curve slope and deformation ...
Jiri Novak
core   +1 more source

Post-irradiation annealing behavior of helium in irradiated Fe and ferritic-martensitic steels

open access: yesNuclear Materials and Energy, 2018
Oxide dispersion strengthened (ODS) alloys, which contain a high number density of nano-scale oxide particles, are supposed to prevent the long-range diffusion of defects therefore enhance irradiation resistance.
S. Chen   +3 more
doaj   +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

Investigation of ion irradiation hardening behaviors of tempered and long-term thermal aged T92 steel [PDF]

open access: yes, 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 ...
Wang, Yanli   +9 more
core   +1 more source

Damage behavior of additive manufacturing 316L stainless steel irradiated with Fe ions

open access: yesNuclear Materials and Energy
The irradiation damage behavior of 316L stainless steel (SS) fabricated using selective laser melting (SLM) and traditional manufacturing (TM) was investigated in terms of microstructural changes in hardness and swelling at RT under irradiation with 3 ...
Jinlei Yang   +5 more
doaj   +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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