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

