Corrosion of 316 SS in Direct Contact with Zircaloy-4 in Repository Relevant Conditions

Key Points

• Corrosion observed at varying rates, suggesting significant material degradation in repository-like conditions.
• Key evidence shows specific corrosion rates of 0.02 mm/year for 316 SS when in contact with Zircaloy-4.
• Assessment using electrochemical techniques within simulated repository conditions addresses corrosion mechanisms.
• Potential compatibility issues highlighted could impact long-term performance of materials in nuclear waste storage.