POST IRRADIATION EXAMINATION OF PRESSURIZED WATER REACTOR STAINLESS STEEL INTERNAL COMPONENTS

Engineering

• Pressurized Water Reactor 100%
• Internal Component 100%
• Stainless Steel 100%
• Mechanical Testing 66%
• Damage Level 66%
• Nuclear Reactor 33%
• Atom Probe Tomography 33%
• Structural Materials 33%
• Load Limits 33%
• Elevated Temperature 33%
• Plant Operation 33%
• Property Degradation 33%
• Induced Precipitation 33%
• Neutron Energy 33%
• Mechanical Stress 33%
• Dislocation Loop 33%
• Energy Spectra 33%
• Mechanical Property 33%
• Fracture Strength 33%
• Electric Power Plant 33%