HCBBS Forum (English)
Submit Chemical Projects / Find Solutions
Amplify Your Requirements on a Broader Chemical Platform *Engineering · Technology · Equipment · Solutions*
Submit Request

High-temperature corrosion of nuclear fuel

2026-07-15View Original

Thread Content

I. Core Background High-temperature corrosion of nuclear fuel is a critical issue for the safe operation of reactors. Following the Fukushima nuclear accident, there has been a significant increase in attention paid to its prevention and control within the industry, and related research continues to advance. II. Main corrosion mechanisms: High-temperature water/steam corrosion: Water under high temperature and pressure is highly corrosive; direct contact with uranium fuel leads to rapid erosion ; Traditional zirconium alloy cladding undergoes a zirconium-water reaction in high-temperature steam, producing large amounts of hydrogen and posing an explosion risk. Differential corrosion due to oxidation of alloy phases: For example, in Cr-doped UN fuel, the UN phase begins to oxidize at 400°C, while the U₂CrN₃ phase starts to oxidize at 430°C; as a result, the UN phase is corroded preferentially, which actually increases the overall corrosion rate, according to international academic research. Corrosion in a liquid metal environment: In lead-cooled fast reactors, element diffusion occurs in the ferritic/martensitic steel cladding within high-temperature liquid lead-bismuth, which damages the surface structure and leads to corrosion. III. Mainstream protection methods: New cladding materials – FeCrAl alloys benefit from a Cr-passivation layer formed on their surface, which greatly enhances their corrosion resistance, and they hold promise as alternatives to traditional zirconium alloys. Surface coating modification: The Cr-Nb alloy coating is suitable for pressurized water reactor conditions, providing effective protection for 45 minutes in high-temperature steam at 1100°C ; A Cr coating with a low grain boundary density can delay the oxidation of the zirconium alloy substrate to over 3000 seconds. Optimization of composition regulation: Adjusting the proportion of carbon in the FeNiCrAl alloy can increase the Cr content in the γ phase, reduce the thickness of the oxide film, and enhance resistance to high-temperature water corrosion.

Submit a Project

**Looking for Chemical Technology, Equipment & Solutions?** No Registration Required Broader Platform Exposure | Global Chemical Service Provider Connections

Submit Request — Free Consultation

Disclaimer

This is an automated machine translation of the original thread. Some technical terms may have inaccuracies; the original text shall prevail. Click "View Original" at the top right to access the source page, which supports IP-based automatic real-time language translation. Please watch out for contact details and sales inducements to prevent fraud. All content and translations are for reference only, representing solely the poster's personal views. For enquiries, email service@hcbbs.com.