ORIGINAL RESEARCH
Accepted on 10 Jan 2025
Effect of microstructure and neutron irradiation defects on deuterium retention in SiC 1
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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Articles
ORIGINAL RESEARCH
Published on 12 Nov 2024
Microstructure, electrical resistivity, and tensile properties of neutron-irradiated Cu–Cr–Nb–Zr
doi 10.3389/fnuen.2024.1486694
- 335 views
ORIGINAL RESEARCH
Published on 16 Feb 2024
Fabrication of neutron absorbing metal hydride entrained ceramic matrix shield composites
doi 10.3389/fnuen.2024.1352667
- 1,768 views
- 1 citation
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Frontiers in Nuclear Engineering
- Nuclear Materials
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