Side-by-side high-temperature accident performance of ATF and conventional claddings in the CODEX-ATF experiment
Abstract
The CODEX-ATF integral bundle test was conducted within the framework of the IAEA Testing and Simulation for Advanced Technology and Accident Tolerant Fuels (ATF-TS) project at the CODEX (COre Degradation Experiment) facility in Hungary. The electrically heated seven-rod bundle consisted of four Cr-coated and three uncoated Zr alloy cladding tubes, enabling a direct comparison of their behavior under high-temperature accident conditions. The experiment primarily aimed to investigate fuel failure and degradation mechanisms.During the test, several rods exhibited ballooning and burst phenomena. The maximum temperature exceeded 1600 °C. The transient was terminated by a bottom-up water quench. The total hydrogen generation was approximately 3 g, indicating substantial oxidation of the zirconium-based components. Intensive Zr–Cr eutectic interaction was observed in the hottest region of the bundle on the Cr-coated claddings. Post-test examinations revealed pronounced deformation and failure in both coated and uncoated claddings.
Fields of Study & Subjects
Nuclear Materials and Properties
Nuclear Engineering Thermal-Hydraulics
Nuclear and radioactivity studies
Publication details
- Journal / source
- Nuclear Engineering and Design
- Volume
- 450
- Pages
- 114770–114770
- Publication date
- 30 January 2026
- Language
- EN