Prediction of electrochemical corrosion potential in PWR coolant for advanced FeCrAl and Zr–4 alloys via radiolysis and mixed potential modelling
Fields of Study & Subjects
Nuclear Materials and Properties
Hydrogen embrittlement and corrosion behaviors in metals
Nuclear reactor physics and engineering
Publication details
- Journal / source
- Journal of Nuclear Materials
- Publisher
- Elsevier BV
- Volume
- 623
- Pages
- 156451–156451
- Publication date
- 10 January 2026
- Language
- EN