Large scale modelling of damage and failure of nuclear graphite moderated reactor

Engineering

• Gas Cooled Reactor 100%
• Lifecycle 50%
• Microstructure 50%
• Fuel Rod 50%
• Induced Change 50%
• Structural Element 50%
• Stress Field 50%
• Safe Operation 50%
• Quasi-Brittle Material 50%
• Impact Behavior 50%
• Core Analysis 50%
• Control Rod 50%
• Safe Life 50%
• Scale Model 50%
• Rigid Structure 50%

Earth and Planetary Sciences

• Gas Cooled Reactor 100%
• United Kingdom 50%
• Scale Model 50%
• Nuclear Reaction 50%
• Brittle Material 50%
• Core Analysis 50%
• Life Cycle 50%
• Control Rod 50%

Material Science

• Stress Field 100%
• Quasi-Brittle Material 100%