Characterization and Behavior of Nuclear Graphite Materials (Q166867): Difference between revisions
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Revision as of 12:13, 8 September 2024
Study of nuclear graphite materials in high-temperature reactors.
- Nuclear Graphite
- Oxidation Behavior
- Microstructural Characterization
- Irradiation Damage
- Thermal Properties
- Raman Spectroscopy
- Pore Structure Analysis
- High Temperature Reactors
- Fracture Behavior
- Decontamination
Language | Label | Description | Also known as |
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English | Characterization and Behavior of Nuclear Graphite Materials |
Study of nuclear graphite materials in high-temperature reactors. |
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