Historical experience providing bases for predicting corrosion and stress corrosion in emerging supercritical water nuclear technology: Part 3-review

Keyphrases

• Corrosion 100%
• Supercritical Water 100%
• Outlet Temperature 100%
• Historical Experience 100%
• Stress Corrosion 100%
• Nuclear Technology 100%
• Supercritical Water Reactor 100%
• Fuel Cladding 75%
• Light Water Reactor 50%
• Fossil Plants 50%
• Material Structure 25%
• Atomic Structure 25%
• Environmental Impact 25%
• Grain Boundary 25%
• Temperature Effect 25%
• Stress Effect 25%
• Plant Water 25%
• Specific Components 25%
• Reactor 25%
• Core Structure 25%
• Surface Temperature 25%
• Ductility 25%
• Reactor Plant 25%
• Water Cooling 25%
• Structural Materials 25%
• Material Temperature 25%
• Nuclear Plant 25%
• Reactor Technology 25%
• Reactor Fuel 25%
• Feedwater Heater 25%
• Reactor Vessel 25%
• Fuel Element 25%
• Film Drop 25%
• Susceptibility to SCC 25%
• Thermal Range 25%
• Dependency Effect 25%

Engineering

• Outlet Temperature 100%
• Light Water Reactors 50%
• Stress Corrosion Cracking 50%
• Past Experience 50%
• Good Agreement 25%
• Isothermal 25%
• Structural Materials 25%
• Fuel Reactor 25%
• Temperature Dependency 25%
• Reactor Technology 25%
• Nuclear Power Plant 25%
• Choosing Material 25%
• Fuel Element 25%
• Reactor Vessel 25%
• Reanalysis 25%
• Phase Composition 25%
• Grain Boundaries 25%

Chemical Engineering

• Reactor Technology 100%
• Film 100%