Post-irradiation SCC investigations on highly-irradiated core internals component materials

Keyphrases

• Post-irradiation 100%
• Constant Load Test 100%
• Internal Component 100%
• Mechanical Behavior 50%
• Power Plant 50%
• Argon 50%
• Material Sample 50%
• Irradiated Materials 50%
• AISI 304 50%
• Test Temperature 50%
• Intergranular Cracking 50%
• Fractograph 50%
• Rate Test 50%
• Failure Time 50%
• Stress Level 50%
• Loading Rate 50%
• Simulated PWR Water 50%
• Stress Effect 50%
• SSRT Test 50%
• Slow Strain Rate Tensile Test 50%
• Stress Curve 50%
• Core Baffle 50%
• Irradiated Steel 50%
• Initial Loading 50%

Engineering

• Stress Corrosion Cracking 100%
• Internal Component 100%
• Test Temperature 50%
• Material Sample 50%
• Rate Test 50%
• Lesser Extent 50%
• Stress Level 50%
• Irradiated Material 50%
• Strain Rate 50%
• Test Environment 50%
• Tensile Test 50%
• Load Test 50%
• Loading Rate 50%
• Electric Power Plant 50%

INIS

• investigations 100%
• irradiation 100%
• pwr type reactors 40%
• simulation 20%
• failures 20%
• levels 20%
• environment 20%
• water 20%
• operation 20%
• cracking 20%
• power plants 20%
• baffles 20%
• steels 20%
• curves 20%
• argon 20%
• strain rate 20%
• shutdown 20%
• loading rate 20%