A5010626570- Nuclear Materials and Properties
- Fusion materials and technologies
- Hydrogen embrittlement and corrosion behaviors in metals
- Radioactive element chemistry and processing
- High Temperature Alloys and Creep
- Microstructure and Mechanical Properties of Steels
- Advanced Materials Characterization Techniques
- Nuclear reactor physics and engineering
- Microstructure and mechanical properties
- Additive Manufacturing Materials and Processes
- Nuclear and radioactivity studies
- Advanced ceramic materials synthesis
- Advanced materials and composites
- Metallurgy and Material Forming
- Ion-surface interactions and analysis
- Hydrogen Storage and Materials
- Nuclear Physics and Applications
- Fatigue and fracture mechanics
- Graphite, nuclear technology, radiation studies
- High Entropy Alloys Studies
- Nuclear materials and radiation effects
- High-Temperature Coating Behaviors
- Rare-earth and actinide compounds
- 3D IC and TSV technologies
- Iron oxide chemistry and applications
Oak Ridge National Laboratory
2020-2025
Government of the United States of America
2023-2024
National Technical Information Service
2021-2023
Office of Scientific and Technical Information
2021-2023
Pacific Northwest National Laboratory
2017-2021
Battelle
2017-2021
Richland College
2020
University of Illinois Urbana-Champaign
2012-2015
Abstract We have made observations of noble metal phase fission-product agglomerates and gaseous xenon within the fuel-cladding interaction (FCI) zone a high-burnup UO 2 fuel. The FCI is boundary between pellet outer surface inner wall oxidized Zr-liner/cladding fuel rod. These are well known to occur spent matrix, although radionuclides been reported by others, we reveal aspects their speciation morphology. That they as discrete particles in Zr liner, suggests occurrence hitherto unknown...
An increase in ductility with radiation dose was observed and investigated during postirradiation evaluation of tensile properties, microstructure, deformation behavior, fracture behavior specimens from a solution-annealed Inconel 718 proton beam window operated at the Spallation Neutron Source. While service, irradiated 940 MeV protons to maximum approximately 9.7 displacements per atom (dpa) calculated irradiation temperature 110 °C. The double-walled sampled after removal samples were...
The ability to acquire high-quality spatially-resolved mass spectrometry data is sought in many fields of study, but it often comes with high cost instrumentation and a level expertise required. In addition, techniques highly regarded for isotopic analysis applications such as thermal ionization (TIMS) do not have the data. Another drawback that radioactive materials, which are interest geochemistry nuclear forensics applications, high-end instruments restrictions on radioactivity...
In-situ mechanical testing in a scanning electron microscope (SEM) equipped with an backscatter diffraction (EBSD) system has quickly gained popularity, particularly because of its rich experimental outcomes. In this work, the advantages and challenges approach are systemized critically discussed relation to irradiated metallic materials novel development. Key observations results evaluated for austenitic stainless steels, additively manufactured (AM) 316 steel, modern accident-tolerant...
Abstract Self‐diffusion is a fundamental physical process that, in solid materials, intimately correlated with both microstructure and functional properties. Local transport behavior critical to the performance of ionic materials for energy generation storage, drives oxidation, corrosion, segregation phenomena science, geosciences, nuclear science. Here, an adaptable approach presented precisely characterize self‐diffusion solids by isotopically enriching component elements at specific...