Nuclear Fuel Development (Q166980)

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This cluster of papers focuses on the development and properties of advanced materials for nuclear fuel, including accident tolerant fuels, fuel cladding, thermophysical properties, oxidation resistance, behavior under high temperature and irradiatio
  • Accident Tolerant Fuels
  • Fuel Cladding
  • Thermophysical Properties
  • Oxidation Resistance
  • Actinide Oxides
  • High Temperature Behavior
  • Density Functional Theory
  • Irradiation Performance
  • Hydrogen Embrittlement
  • Fission Product Release
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English
Nuclear Fuel Development
This cluster of papers focuses on the development and properties of advanced materials for nuclear fuel, including accident tolerant fuels, fuel cladding, thermophysical properties, oxidation resistance, behavior under high temperature and irradiatio
  • Accident Tolerant Fuels
  • Fuel Cladding
  • Thermophysical Properties
  • Oxidation Resistance
  • Actinide Oxides
  • High Temperature Behavior
  • Density Functional Theory
  • Irradiation Performance
  • Hydrogen Embrittlement
  • Fission Product Release

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