ORIGINAL RESEARCH
Published on 10 Feb 2025
Effect of microstructure and neutron irradiation defects on deuterium retention in SiC
doi 10.3389/fnuen.2025.1534820
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- Frontiers in Nuclear Engineering
- Nuclear Materials
- Research Topics
- Advances in Fusion Materials Development
Advances in Fusion Materials Development
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ORIGINAL RESEARCH
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Microstructure, electrical resistivity, and tensile properties of neutron-irradiated Cu–Cr–Nb–Zr
doi 10.3389/fnuen.2024.1486694
- 1,625 views
- 2 citations
ORIGINAL RESEARCH
Published on 16 Feb 2024
Fabrication of neutron absorbing metal hydride entrained ceramic matrix shield composites
doi 10.3389/fnuen.2024.1352667
- 3,071 views
- 10 citations
