Modern measurement of local radial thermal conductivity of irradiated he-bonded U-10 wt. % Zr annular fuel: A cross-correlative study with electron probe microanalysis techniques
Fields of Study & Subjects
Nuclear Materials and Properties
Fusion materials and technologies
Nuclear reactor physics and engineering
Publication details
- Journal / source
- Journal of Nuclear Materials
- Volume
- 624
- Pages
- 156487–156487
- Publication date
- 28 January 2026
- Language
- EN