Characterization and Behavior of Nuclear Graphite Materials (Q166867): Difference between revisions

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Nuclear Graphite
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Oxidation Behavior
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Microstructural Characterization
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Irradiation Damage
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Thermal Properties
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Raman Spectroscopy
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Pore Structure Analysis
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High Temperature Reactors
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Fracture Behavior
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Decontamination

Latest revision as of 20:17, 12 September 2024

Study of nuclear graphite materials in high-temperature reactors.
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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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